Graphical Representation of Transmutation and ... - CiteSeerX

JAERI 1280

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Graphical Representation of Transmutationand Decay Chain Data, Transmutation Cross

Section and Delayed Gamma Ray Emission Data

September 1982

Japan Atomic Energy Research Institute

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Board of Editors

Hiromichi Adachi

Muneo Handa

Akihiko Ito

Hiroshi Mitsui

Takao Numakunai

Konomo Sanokawa

Sanae Tamura

Kaoru Ueno

Shigeru Mori (Chief Editor)

Taknmi Asaoka

Masao llara

Masanori Kanbara

Ryukichi Nagasaki

Jiro Okamoto

Kazuo Sato

Masatoshi Tanaka

Toyojiro Fukcta

Makoto Ishizuka

Isamu Kuriyama

Hideshiro Nakamolo

Hiroshi Sakurai

Eiji Shikata

Shigeya Tanaka

JAERI w.tC- H±,

(=r3l9-ll 3?«m

JAERI reports are reviewed by the Board of Editors and issued irregularly.Inquiries about availability of the reports should be addressed to Information Section,

Division of Technical Information, Japan Atomic Energy Research Institute, Tokaimura,Naka-gun. Ibaraki-ken 319-11, Japan.

©Japan Atomic Energy Research Institute, 1982

m

JAERI1280

Graphical Representation of Transmutation and

Decay Chain Data, Transmutation Cross

Section and Delayed Gamma Ray Emission Data

Yasushi Seki, Hiromasa Iida and Hiromitsu Kawasaki

Division of Thermonuclear Fusion Research


Tokai-mura, Naka-gun, Ibaraki-ken

Received April 8, ! 982

Abstract

In a D-T burning fusion reactor, the neutron induced activity severely limits personnelaccess to the reactor. Accurate evaluation of the induced activity and dose rate is necessary toconduct effective biological shield design. In order to evaluate the dose rate accurately,considerable amount of activation data is required. This report gives graphical representationof transmutation and decay chain data, transmutation cross section data and delayed gammaray emission data for 116 nuclides of interest in terms of fusion reactor design. This graphicalrepresentation was made with hope of producing a reference for examining activation pro-blems. It has already been shown to be effective in correcting inappropriate data. A computercode AMOEBA developed for the checking and plotting of the activation data is also describedin this report.

Keywords: D-T Neutron, Fusion Reactor, Induced Activity, Transmutation, Cross Section,Decay Chain, Delayed Gamma Ray, Biological Dose, Graph Plotting, Data.

• Century Research Center, Ltd., Co.

JALR1 1280

1982 i£ 4 fl 8 B 5 a

i - K AMOEBA

- {Iff.)

11

核種変換と崩壊連鎖データ，核種変換断面積と

遅発ガンマ線放出データの図形表示

日本!京 fjJ研究所核融合研究部

関泰・飯田浩正・川崎弘光ホ

1982年 4月日日受理

要旨

JAERl1280

D-T綿焼の核融合がにおいて誘導放射能の存在:は炉停止時の従業員の近接を者 Lく制限する.

効率良く生体遮厳を行うためには携導放射能と線鼠率を精度良く評価する必袋がある.そのため

にはかなりの.の放射化データが製求される.本報告書は骸融合炉の投.Hの観点から必要とされ

た 116 依楯の依極変換と跡1地盤連鎖データ.紘禰~換断i!ñ楠と遅発カン 7線放111 デーヲを閃形J，iJJ;

して与える.ζ の凶形表示作業は級晴;1化の!日1岨を調べるための怠身資料をリえる ζ とを1-1的とし

てはされた.本作業自体が不適当 fi.デ一世を修正する上で訂mであった.

放射化データの検証と図形表示をhうために開発した計算コード AMOEBAについても紹介す

る.

- センチュ')・リサーチ・センヲー(練}

JAERI 1280 „

Contents

1. Introduction 1

2. Data Libraries 2

2.1 CHAINLIB, Transmutation and Decay Chain Data Library 2

2.2 CROSSLIB, Transmutation Cross Section Library 7

2.3 GAMM ALIB, Delayed Gamma Ray Emission Data Library 8

3. Graphs of Activation Data 12

4. Concluding Remarks 246

Acknowledgements 246

References 247

Appendix Activation Data Checking and Plotting Code, AMOEBA 248

A.1 Function 248

A.2 Program Structure and Subroutines 248

A.3 Input Instruction and Output Descriptions 250

JAERI 1280

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2.1 CHAINLIB. ®WiM&tMm®t&T-9y4 7 7>)- 2

2.2 CROSSLIB, &S!2£$Kfi>lfrrtMfii7 •< 7 '^ 'J - 7

2.3 GAMMALIB. j i £ # > v f 8 K M J i T - ? 7 -f 7'v M - 8

3. M-UtT-9<r.-mB&'l< 12

4. IS ;f 246

Mt S? 246

»%m 247

ft U: MHtr- 9<r>*s. y '; tWA&Kti'G-^- !•'. AMOEBA 248

A.1 fl* (i 248

A.2 7 o ' /7 Afl||j£±H>-7''i>-f' > 248

A.3 A/ l i l lWjwM! 250

JAER1 1280

1. Introduction

In a D-T burning fusion reactor, the radioactivity induced by the 14 MeV neutrons limitspersonnel access to the reactor even after shutdown. The biological dose rates from the neu-tron induced activity of various components of fusion reactor have been evaluated by severalresearchers.'>'5) A code system THIDA 6 ) has been developed in the Japan Atomic EnergyResearch Institute (JAERI) for the calculation of exposure dose rate around a fusion device.It consists of radiation transport codes, induced activity calculation code and data libraries fortransmutation ar.d decay chain, transmutation cross section and delayed gamma ray emission(see Fig. 1). This THIDA code system has been applied to calculate dose rates around severalfusion devices l ) > 5 ) and it has been also tested for a stainless steel sample activationmeasurement using 14 MeV neutron source. 7 ) Through these applications several data errorsin the data files have been identified and corrected. In order to further check and review thecontent of the huge amount of data in the libraries, an activation data checking and plottingcode called AMOEBA has been developed. By utilizing the checking and plotting capabilitiesof the AMOEBA code, the consistencies of the libraries have been checked and the activationdata of the 116 stable nuclides have been plotted. Graphical representation of the dataproved to be effective in correcting inappropriate data. In addition, the compilation of thegraphs is found to be a convenient tool in the investigation of activation problems, for instancein identifying the source of induced activity from an irradiated material.

This report describes in Section 2, the data library structures of transmutation and decaychain, transmutation cross sections and delayed gamma ray emission data incorporated in theTHIDA code system. Graphical representations of the activation data for 116 stable isotopesdrawn by the AMOEBA code are shown in Section 3. The function and program structureof the AMOEBA code are described in the Appendix.

* transmutation and decay chain data for 116 stable nuclides, about 800 transmutation cross sectionsand gamma ray emission data of about 300 unstable nuclides.

Graphical Representation of Transmutation and Decay Chain Data Transmutation IAPHI nanCross Section and Delayed Gamma Ray Emission Data ' A t R 1 ' i B U

2. Data Libraries

Induced activation calculations for fusion devices have been carried out on the basis of acalculational flow shown in Fig. 1. The whole network of data libraries and computer codes,the THIDA system calculates Transmutation, Hazard Potential, Induced Activity, Dose Rateand Afterheat. In this section, the structures of the following data libraries for 116 stablenuclides of interest in terms of fusion reactor design are described:

(1) CHAINLIB for transmutation and decay chain data,(2) CROSSLIB for transmutation cross section data,(3) GAMMALIB for delayed gamma ray emission data,

In the CHAINLIB and GAMMALIB data libraries, the nuclides are denoted using 5 digitsin the following manner.

X X | X

Z !M

X XA

where Z and A are the atomic and mass numbers of the nuclide, respectively. M is a metastableindicator which takes I for metastable state and 0 otherwise. When three digits are requiredto denote A, only the last two digits are given (e.g. 82003 for 'SiPb).

2.1 CHAINLIB, Transmutation and Decay Chain Data Library

In principle, this data library was produced based on the following guidelines:(1) Only the primary transmutation reactions by neutron are considered. That is, neutron

reactions w<th stable (long-lived naturally occuring) nuclides are considered but theneutron reactions with reaction product nuclides are neglected. (The exceptional cases arethe 13C produced from the l2C(n, y) reaction and S1V produced from the s2V(n, 2n)reaction. ) This guideline is adopted to avoid the complexity introduced by secondaryreactions. However, the secondary reactions may be included if desired. When dealingwith very high irradiation fluence, the secondary reaction should be properly consideredbut in usual applications their effects are generally insignificant.

(2) Transmutation reactions considered are the ones with experimental data or evaluation(s)inCINDA75 8 ) .

(3) Production of metastable nuclides is also considered using branching ratio.(4) Decay chains of unstable nuclides are followed until they end up with stable nuclides

listed in Table 1.(5) Only transmutation reactions are included. Inelastic reactions resulting in metastable state

are not included because such metastable nuclide is mostly short-lived. They will beincluded in future if necessary.

The data structure of the CHAINLIB library is descrbed below.#1 (112, E12.0)

IP AIR ; the number of #2 cards required to describe the transmutation and decaychain of the nuclide being considered.

ABUND ; natural abundance of the nuclide in percent.

JAERI 1280 2. Data Libraries

/Coupled 42 - Group Neutron and 21 - GroupGamma Roy Cross Section Set , GICX40 J

/ Activation CrossSections, CROSSLIB

/Decay Chain Data,1 CHAINLIB

/Delayed Gamma RayYield, GAMMALIB

/ 54-Group Gamma Ray'Cross Sections. GROUPIN

/ Flux to DoseConversion Factor

Neutron Transport Calculation,AN1SN , D O T - 3 . 5

T/Neutron Flux Distribution /

Induced Activation CalculationA C T 4

Decay Heatduced Activity

1i t y /

Gamma Ray Transport Calculation,A N I S N , D 0 T - 3 , 5

T/Gommo Roy Flux Distribution /

tShutdown Dose Calculationand Plotting , APPLE

Dose Distribution andGamma Ray Spectra Plot

Fig. 1 Plow chart of calculation of induced activation and dose rate.

#2 (El 2.0, A8, 4X, 2E12.0, El 1.0, Al, El 2.0)ZAP ; the name of the parent nuclide (Z, M, A) (see the note in the previous page).ACTYP ; the symbol of the transmutation reaction or the decay scheme (see Table 2

and the note below).ZAD ; the name of the daughter nuclide (Z, M, A) (see the note in the previous

page).BETA ; branching ratio.TIME ; half life of the nuclide specified by ZAP.UNIT ; the unit for the half life (S, M, H, D, W, G and Y corresponding to second,

minute, hour, day, week, month and year, respectively).EMEAN ; mean energy of the emitted 0 ray.

#3 (112)KKM ; the number of transmutation reactions to be treated in the CROSSLIB

library for the parent nuclide specified by ZAP.

Data in cards #1 ~ #3 are repeatedly given for each of the stable nuclides. The number of#2 cards is specified by IP AIR. By using #2 cards, first the transmutation reaction data of thestable nuclide are given followed by the decay data of unstable product nuclides. Decay chainsare followed until they end up with stable nuclides given in Table 1.

Graphical Representation of Transmutation and Decay Chain Data, Transmutation IAPRI n a nCross Section and Delayed Gamma Ray Emission Data '

Table 1 List of stable or long-lived naturally occurring isotopes fromthe Chart of Nuclides 9 )

Element Name of isotopes

H 100I I002He 2003 2004Li 3006 3007Be 4009

B 5010 5011C 6012 6013N 7014 7015

O 8016 8017 8018F 9019

Ne 10020 10021 10022Na 11023Mg 12024 12025 12026Al 13027

Si 14028 14029 14030P 15031S 16032 16033 16034 16036C'l 17035 17037

Ar 18036 18038 18040K 19039 19040 19041

Ca 20040 20042 20043 20044 20046 20048Sc 21045Ti 22046 22047 22048 22049 22050V 23050 23051Cr 24050 24052 24053 24054Mn 25055Fe 26054 26056 26057 26058Co 27059Ni 28058 28060 28061 28062 28064Cu 29063 29065Zn 30064 30066 30067 30068 30070Ga 31069 31071Ge 32070 32072 32073 32074 32076As 33075Se 34074 34076 34077 34078 34080 34082Br 35079 35081Kr 36078 36080 36082 36083 36084 36086Rb 37085 37087Sr 38084 38086 38087 38088Y 39089Zr 40090 40091 40092 40094 40096Nb 41093Mo 42092 42094 42095 42096 42097 42098 42000TcRu 44096 44098 44099 44000 44001 44002 44004Rh 45003Pd 46002 46004 46005 46006 46008 46010Ag 47007 47009Cd 48006 48008 48010 48011 48012 480i3 48014 48016In 49013 48015Sn 50012 50014 50015 50016 50017 50018 50019 50020 20022 50024Sb 51021 51023Te 52020 52022 52023 52024 52025 52026 52028 52030I 53027Xe 54024 S4026 54028 54029 54030 54031 54032 54034 54036


Table 1 (continued)

Element Name of isotopes

Cs 55033

Ba 56030 56032 56034 56035 56036 56037 56038La 57038 57039Ce 58036 58038 58040 58042Pr 59041Nd 60042 60043 60044 60045 60046 60048 60050PmSm 62044 62047 62048 62049 62050 62052 62054Eu 63051 63053Gd 64052 64054 64055 64056 64057 64058 64060Tb 65059Dy 66056 66058 66060 66061 66062 66063 66064Ho 67065Er 68062 68064 68066 68067 68068 68070Tm 69069Yb 70068 70070 70071 70072 70073 70074 70076Lu 7107S 71076Hf 72074 72076 72077 72078 72079 72080Ta 73080 73081W 74080 74082 74083 74084 74086Re 75085 75087Os 76084 76086 76087 76088 76089 76090 76092Ir 77091 77093Pt 78090 78092 78094 78095 78096 78098Au 79097Hg 80096 80098 80099 80000 80001 80002 80004Tl 81003 81005Pb 82004 82006 82007 82008Bi 83009

Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAER1 1280

The symbols used to denote the nuclear reactions and decay chain are shown in Table 2together with the changes in atomic number Z, metastable state indicator M and massnumber A.

The name of transmutation reactions and decay scheme (ACTYP) are denoted by 8characters at most (A8). The name of a transmutation reaction should coincide with the oneused in the transmutation cross section library CROSSLIB. In principle, the name of a reactionis formed as follows.(1) Firstly the name of the parent nuclide is given, (e.g. Cl 2 is used to denote (,C)(2) Secondly the symbol of the reaction type is given as described in Table 2. When the

reaction produces a metastable nuclide, M is added to the symbol of the reaction type.For example, 60Ni (n, p) 60mCo will be denoted as NI60NPM.

The symbol of a decay type is given as shown in Table 2. Decay type other than the 7 typeslisted in Table 2 is denoted by ETC.

As an exan pie, the library data for Li, 7Li, 'Be is shown in Table 3.

Table 2 Change in atomic number, stabk/mctastablcstate indicator and mass number involved intransmutation reaction and decay

Reactiontype

(n, y)(n, p)(n,a)(n,d)(n, n'd)(n,t)(n, 2n)(n, 3n)(n, n'p)(n, n a)(n,3He)(n, n't)(n, 2n'p)

Decaytype

(3 + decay(3 — decay

Transmutation reaction

Symbol

NGNPNANDNNDNTN2NN3NNNPNNANHE3NNTN2NP

Symbol

B+B-

Isomeric transition ITElectron capture

0-a decay2a decaya decayOthers

ECB-A2AA

ETC

Atomicnumber,

AZ

0-1- 2-1-1-1

00

-1- 2- 2-1-1

Decay mode

Atomicnumber,

AZ

_ |

+ 10

-1-1-A

- 2-

Melastablcstate,M*

0000000000000

Metastablestate.

M*

00

1*00000

-

Massnumber,

AA

10

- 3-1-2- 2- 1- 2— I_4_2—3_ f

Massnumber.

AA

0000

- 4- 8- 4

-

*M changes from 0 to I whenever a reaction produces a metastable nu-clide, for example for 6 0 Ni (n, p) 6 0 m C o , the symbol for this reaction isNPM and M changes from 0 to 1.


Table 3 Example of the CHAINLIB library data for the transmutation and decay chainof 6Li, 7 Li and9 Be

9 0.0753006LI06NA30063006LI06N2NP30063006LI06NP30063006LI06NG1003B-20068-

412 0.925

3007LI07NNA30073007LI07ND30073007LI07NNP30073007LI07N2N3007LI07NG1003B-2006B-3008B-4008A

516 1 .0

4009BE09NA40094009BE09ND40094009BE09N2N4009BE09NP40094009BE09NG4009BE09NT40091003B-2006B-3008B-3009B-4010B-4008A

100320042004100120061001300720033006

1003200420061002200610013006300B2003300640082004

2006200430081002400830091001401030071003200330064008400950102004

0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.1.

0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1.

.10000E+01,0,10000E+01,010000E+01010000E+0110000E+0110000E+01

10000E+01010000E+01010000E+01010000E+0110000E+0110000E+0110000E+0110000E+010

10000E+01010000E+01010000E+0110000E+010lOOOOEtOl10000E+01010000E+0110000E+0110000E+0110000E+0110000E+010

0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.

,00000001260E+02Y8600E+00S

000000001260E+C2Y8600E+00S88O0E+00S67 E-16S

00000000001260E+02YB600E+00S8800E+OOS1760E+00S2500E+07Y67 E-16S

0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.

.0

.00.00.00

0000010000000200000003000000040000000410000005000000060000000700

62000E-020000080011690E+0100000900

00000000

0000100000001100000012000000130000001400000015000000160000001700

ooooiaoo00002000

62000E-020000210011690E+010000220043330E+01000023000

0000000000

0000240000002500000026000000270000002800000029000000300000003100000032000000330000003S000000360000003610

62000E-020000362011690E+010000370043330E+010000380045400E+010000390018500E+00000040000 0000'100

2.2 CROSSLIB, Transmutation Cross Section Library

This library consists of neutron cross section data in the 42-energy group structure ofthe GICX40 library,I0) which is shown in Table 4. In calculating transmutation reaction rates,this correspondence of the energy structure permits direct use of the CROSSLIB library withthe neutron flux obtained by the use of the GICX40 library.

The transmutation cross sections are obtained from the Ref. 11-21. In principle, thedata included in the evaluated nuclear data file ENDF/B-4 I5> are adopted with the firstpriority among others. Processing codes SPTG4Z 22> and NJOY 23) are used to derive 42-group cross sections from the ENDF/B-4. Infinite dilution is assumed for processing theresonance parameters and the 1/E weighting is used for constructing 42-group cross sections.Cross section data not available in ENDF/B-4 are read from the graphs or taken from tablesin various publications. We are fully aware of the incompleteness of the CROSSLIB libraryand that some of the data are not very accurate. We tried to put some values rather than havingnone. The present version of the library should be considered as a starting point and extensivere-evaluation and updating of the library is intended.

„ Graphical Representation of Transmutation and Decay Chain Data, Transmutation , . „ , , ->Qn

" Cross Section and Delayed Gamma Ray Emission Data J AUKI i i»u

The data structure of the CROSSLIB library is shown below:#1 (A8.4X.I12, 5A8)

ACTYP ; the symbol of the transmutation reaction (t'.ie symbol corresponds tothe ACTYP in the CHAINLIB library)

IX ; the number of group cross section data CS(I) used to represent thereaction cross section (default value of IX is 42)

REFER(l) ; the symbol representing the data source from which the data wereobtained and the year when the data source was published. (Table 5)

#2 (6E12.0)CS(I), 1=1, IX ; the cross section data for the IX groups of the ACTYP reactionTwo types of data #1 and #2 are repeated for KKM reactions as specified in the

CHAINLIB #3 data.An example of the CROSSLIB library content is given in Table 6.

2.3 GAMMALIB, Delayed Gamma Ray Emission Data Library

This library stores the energies and the intensities of the gamma rays emitted fromradioactive nuclides which are produced as the result of transmutation reactions. All data in-corporated in this library is obtained from the Seventh Edition of the Table of Isotopes.24'

The data structure of the GAMMALIB library is shown below:#1 (A4,18,112)

ADA ; usually left blank except at the end of the library where 'END' iswritten.

IZAA ; the name of the nuclide emitting gamma ray(s). IZAA corresponds toZAP in the CHAINLIB library. The methodology for IZAA specifica-tion is described at the beginning of Section 2.

INDX ; the number of gamma ray species emmitted from the nuclide IZAA#2 (6E12.0)

ENEG(I) ; energy of the I-th gamma-ray in eVINT(I) ; intensity of the I-th gamma-ray (1.0 means 100% emission)1=1, INDX

Two types of data #1 and #2 are given for each gamma-ray emitting nuclide.An example of the GAMMALIB library data is shown in Table 7.

JAERI1280 2. Data Libraries

Table 4 The 42-group neutron energy group structure adoptedin the CROSSLIB and GICX40 libraries

Group Energy Limits Mid-Point Energy

123456789

1011121314IS161718192021222324252627282930313233343536373839404142

15.000 -13.720 -12.549 -11.478 -10.500 -9.314 -8.261 -7.328 -6.S00 -5.757 -5.099 -4.516 -4.000 -3.162 -2.5P0 -1.871 -1.400 -1.058 -0.800 -0.S66 -0.400 -0.283 -0.200 -0.141 -

100.046.521.510.04.65 -2.15 -1.00 -0.465 -0.215 -

100.046.521.510.0 -4.65 -2.15 -1.00 -0.465 -0.215 -

13.72012.54911.47810.5009.3148.2617.3286.5005.7575.0994.5164.0003.1622.5001.8711.4001.0580.8000.5660.4000.2830.2000.1410.100

46.521.510.04.652.151.000.4650.2150.100

46.521.510.04.652.151.000.4650.2150.001

MeV

keV

eV

14.36013.13512.01410.9899.9078.7887.7956.9146.1295.4284.8084.2583.5812.8312.1861.6361.2290.9290.6830.4830.3420.2420.1710.121

73.2534.015.757.3253.401.5750.7330.3400.158

73.2534.015.757.3253.401.580.7330.3400.108

MeV

keV

eV

10 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAER1 1280

Table 5 List of the data source of the cross sections adopted in the

CROSSLIB library

Symbol of data sourceName of author/editor/compiler Reference number

KAPL-3327JU-RR-3ENDF/B-3

N. D. T,11ENDF/B^KFK-2233A.NL-75-34NSE 58

BNL 325JAERI-M6354

K.FK-2386

196719701973

19731974197519751975

1976

19761977

J.T. Reynolds et al.H. Leppaemaeki et al.M.K. Drake

W.E. Alley et al.M.K. Drake

B. Goel et al.W.G. Davey et al.W.G. Gross et al.D.I. Garber et al.K. TsukadaB. Goel et al.

U )12)

13)

14)IS)16)17)18)

19)20)21)

Table 6 Example of the CROSSLIB library data

LI06NA0.25464E-010.509376-010.123076*000.29935E*000.?0433k»000.57S00E+010.57591E+02LI06NP0.703*16-020.14741E-010.14015E-01

L106NG0.10165E-040.104706-040.10873E-040.11782E-040.23594E-040.23594E-030.23594E-02LI07NNA3.261 E-01• •236 E-011.028 E-02

LI07ND0.10530E-01

L107N2N0.22312E-01

L107NP0.0LI07NG0.10000E-040.10000E-040.10000E-040.1000CE-040.26450E-040.241426-03O.22OO4E-0286 09 MA0.10540E-010.30142E-010.9405SE-010.90523E-04BE09NL)0.0

42ENDF/8-4O.27«85E-O1 0.31204E0.58299E-U1 0.66775E0.15982E+00 0.22277E0.43720E + 00 0.11063E0.89669E + 00 J.12648E

0.84S92E*C2 0. 12422E13ENDF/d-*

0.79772E-02 0.90186E0.17602E-01 0.21115E

197*-01 0.34*416-01-01 0.7b?67E-0100 O.;:575CE*OO01 0.,;V3el£»0101 0.ie295E«01

+ C2 O.lt>2CO£«O2+ 03 0 .1 l:.2 lbl-*031974-02 0.9V6*l t -02-01 0.26155E-01

0.38724E-01 0.••6356-010.673536-01 0.10007E*00

0.i:U<>6£ + 01 0.757126*000.2b7t5E*01 0.39216E»010.267S7E*02 0.39266E*020.267556*03 0.82661E*03

C. 112056-01 C.1JI664E-010.28643E-01 0.34248E-01

•2EN0F/8-* 197*0.10208E-0+ O.1O252E-O* 00.10530E-04 0.10S91E-04 00.10996E-0* 0.11136E-0* 00.11981E-0+ 0.1218Ê-04 00.34653E-04 0.50882E-04 0.0.34653E-03 0.50881E-03 0.0.34653E-02 0.50881E-02 0.

1+EN0F/B-* 197*01 3.796 E-01 • .01 3.B56 E-01 3.

-0+

A0296E-0* 0.110653E-04 0.10716E-04 0.10779E-04

14 0.11447E-04 0.11602E-0414 0.14963E-04 0.17793E-04

74612E-04 0.10958E-03 0.16090E-0374612E-03 0.10958E-02 0.16090E-0274612E-02 0.10958E-01 0.338SSE-01

3..530 E• ..157 E9..262 E

0.80586E

0.20971E

0.10000E0.10000E0.10000E0.10000E0.45269E0.3+839E0.32520E

0.12885E0.37289E0.100 54E

005 E-01 4.1*2025 E-01 1.399

E-0! *«201E-01 • •3 *0

E-01E-02

-* 197402 0.49108E-02 0.6ENOF/3-* 1974

01 0.18799c"-Cl C.1

27772E-C2 C.8bV59E-C3 0.34941£-C4

15674E-01 0.7b289E-02 0.10358E-02

426NUF/8-4-04 0.10000E-04 0.10000E-04 0.1C00OE-04 0.10000E-04 0.77444E•03 0.50264E-02 0.48051E19ENUF/B-4

•01 0.15155E•oi a.4e•00 0.594S5E

1974-04 0-04 0,- 0 * 0,-04 0,-04 0,-03 0,-02 0,1974-01 0,-01 0.-01 0.

1G000E-04 0.10000E-04 0,100COE-04 0,10000E-04 0.112466-03 0.72426E-03 0.7C570E-02 0.

10000E-0410000E-0410000E-041C295E-0414174E-03104 52E-0210338E-01

0.10000E-04C.1C0O0E-040.1COOC£-040.19180E-040.17863E-O30.15C79E-02C.31579E-01

17483E-01 0.2O065E-01 C.23917E-0158916E-O1 C.6923CE-01 C.80107E-01235B7E-01 0.6S3216-C2 C.236ieE-O2


Table 7 Example of the GAMMALIB library data

0.28

1.772J4.66626.790J

3.23

3.6*

3C09• 07

4011! +061 +06i +06

SC12+ 06

5013• 06

60155.29387 +066.5714

0.511

1.726.056.87

8.71

0.511

1.11.454.19

0.511

1.634

4.4012.545

3.51

• 067013

• 0 67016

• 06• 06+ 06

7017+05

6015• 06

6019• 05• 06• 06

9016• 06

9020+ 06

10023• 05+ 06

11021+05

110221.27455 +06

1.36664.2369

1.4723

3.89661.37972.2156

1.00291.809

11024+06+ 06

11124• 05

11025+ 05• 06• 0 6

11026• 06• 06

0

000

0

0

00

2

000,

0 ,

2 ,

.1

.002 6

.0200

. 0 4 5 1

. 6

.076

. 6 8. 4 2

. C

.1032

.1194

.82584

.030

. 0

02- C l

M

2-C4

1

6

-C41

7- 0 2- 0 3- 0 3

2

1

a0.0366560 ,0,

1 ,

1 ,

0 .0 ,

0 ,

C.

1 .0 .

1 .

0 .0 .0 .

0 .0 .

.031467

.12853

.938

. 0

.329

.27184

.051

,999 34

,0.84

.0

.13137

.26921,10445

829P9

- 0 2l

2

5

- 0 32

2

4

- 0 51

b

- 0 2- 0 2

10- 0 2

0

y

57

4

79

16

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11 ,2 .

3 ,

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3 ,

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5 .1 .2 .

1 .1 .

.2 *29 • C7

( S - . 3 - A ).1248.0193.9747

.43891

.2011

.R500

. 9 0

.1292

.1642

. 9 7

. 5 5

. 5 9

.334

.639

.VaS

.511

.511

.7541

,85066117

.fcGOb

13t<967

• C6

• 06+ 06

+ 06

• 06+ 06

• 06+ 06

+ 06

• 05• 06• 06

• (.'»•

• O t

+ C6

• 06

vC6

• 06

• 05• Cfr• Ot

• 06• Cf

0

000

0

00

00

0

c,0,0 ,

0,

0 ,0 ,

2 ,

1 .

1 .

c.0 .0 .

3 .

.i'i

. 3 3

.004 7

.0174

.0129

. 7 4

. 3 1

.344

.666

.3176

.92126

.01468

.286

. 1 7

.9906,36044

,C

,R

0

126430V7685 84C3

057676C.019C

- 0 4- 0 3

- 03

- 0 2

- 0 3

- 0 3

- 0 2- 0 3

• 00

• 00

- 0 3

25

8

27

1,1,

2 .

3 .

9 .1 .

1 .2 .

• 6921.8519

.3129

. 7 5

.11515

. 3 6

. 5 6

.C7V

,6672

7 5 29651

4122133

+ C6• 06

• 06

+ 06+ 06

• 06+ 06

• 06

• 06

• 05• 06

• 06+ 06

c0

0

c

00

0

c.

0 .0 .

c.I ' .

. 9 3

.0213

. 3 2

.6944

.04783

.55

.268

. 10266

. 6 1

,147,164 76

0320559457

- 0 3

- 0 3

- 0 2

-03

- 0 2

-OS

- 0 2

- 0 2

, , Graphical Representation of Transmutation and Decay Chain Data, Transmutation . , P D , , , a n

Cross Section and Delayed Gamma Ray Emission Data J Afciu i iou

3. Graphs of Activation Data

In this section, the plotted output of the transmutation and decay chain diagram, thetransmutation cross sections and delayed gamma ray data are given for each of the 116 stablenuclides listed in Table 8. Table 8 also gives the natural abundance and the page where theplotted data can be found.

Transmutation and decay chain diagram for a nuclide is shown on an even numbered pageand transmutation cross section and delayed gamma data for the nuclide are shown togetheron the next odd numbered page. Descriptions of the plotted output are given first.Plotting output descriptions

(1) Transmutation and decay chain scheme plotting outputThe symbols for transmutation reaction type and decay mode type are described in

Table 2.A solid line arrow shows a transmutation reaction, the name of which is written above

the line. Each arrow shows a neutron reaction with the stable nuclidc, the symbol of which isplaced inside a rectangle.

A dotted arrow shows a decay of an unstable nuclide with the decay mode and itshalflife. For the multiple decay mode branching ratio is shown in parentheses.

When two types of reactions or decay modes result in the same daughter nuclides, e.g.(n, np) and (n, d) reactions or 0+ decay and electron capture, both of the reactions or decaymodes are shown in smaller letters.

Metastable nuclides are shown with symbol M beside the mass number.(2) Transmutation cross section plotting output

Transmutation reactions for a stable nuclide included in the CROSSLIB library areplotted in the multigroup form. All the reactions with non zero values for the nuclide in thelibrary are plotted on a single graph. A symbol mark is assigned to each of the plotted crosssections and its identification is given below the graph. The data reference of the cross sectionsis also shown in parentheses by the symbol described in Table 5. The name of the reactionswith only zero values in the CROSSLIB library are also shown below the graph without anysymbol mark.

(3) Delayed gamma ray emission data table outputAll the unstable nuclides in the CHAINLIB library for a parent stable nuclide are listed

in the decay gamma-ray table. The energies and intensities of gamma rays with intensitygreater than 0.1% per decay are tabulated. Up to 10 strongest gamma rays are tabulated for adecaying nuclide. The annihilation radiation, 0.511 MeV, from 0+ decay is always given firstwhen it exists. Unstable nuclides without any delayed gamma ray emission are given in thetable with their half lives.

JAER11280 2. Data Libraries 13

Table 8 List of stable nuclides for which the activation data are plotted

Element

LiBe

B

C

N

OFNa

Mg

Al

Si

P

C

Cl

K

Ti

V

Cr

Mn

Fe

Co

Ni

File

No.

1234567891011121314IS16171819202122232425262728293031323334353637383940414243444546474849505152535455565758

Nuclide

number

30063007400950105011601260137014701580168017901911023120241202512026130271402814029140301503116032160331603416036170351703719039190401904120040200422004320044200462004822046220472204822049220502305023051240S0240S224053240542505526054260562605726058270592805828060280612806228064

Naturalabundance

(%)

7.592.5100.019.880.298.891.11

99.630.366

99.760.038

100.0100.078.9910.011.01

100.092.234.673.10

100.095.020.754.210.017

75.7724.2393.260.01176.73

96.940.6470.1352.090.00350.1878.27.4

73.75.45.20.25

99.754.35

83.799.52.36

100.05.8

91.82.150.29

100.068.326.11.133.S90.91

Page of

plotted data

14161820222426283032343638404244464850525456586062646668707274767880828486889092949698100102104106108110112114116118120122124126128

Element

Cu

Zn

Zr

Nb

Mo

Cd

In

Sn

Sb

Hf

Ta

W

Pb

Filr

No.

596061626364656667686970717273747576777879808182838485868788899091929394959697989910010110210310410S106107108109110111112113114IIS116

Nuclide

number

290632906530064300663006730068300704009040091400924009440096410934200042092420944209S4209642097420984800648008480104801148012480134801448016490134901550012500145001553016

soon5001850019500205002250024510215102372074720767207772078720797208073081740807408274083740847408682004820068200782008

Naturalabundance

(%)

69.230.848.627.94.118.80.62

51.511.217.117.42.8

100.09.614.89.315.916.79.6

24.1I.2S0.89I2.S12.824.112.228.77.54.3

95.71.010.670.3814.87.7S

24.38.6

32.44.S6S.64

57.342.70.165.218.627.113.73S.2100.00.13

26.314.330.728.61.42

24.122.1S2.3

Page of

plotted data

13013213413S138140142144146148ISO1S21.54168156IS8160162164166170172174176178180182184186188190192194196198200202204206208210212214216218220222224226228230232234236238240242244

14 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data

'He NP

TI".F6S"

Abundance7.50'/.

JAERI1280 3. Graphs of Activation Data J5

T R n N 5 M U T R T I 0 N C R 0 5 S

Iffio-3 icrl

• NR (EHDF/B-4 I 9 K• KI2NP I

1 OP 1O1 1O2 1O3 IO4

NEUTRON ENERGY (EV)1 B KIP IEUDF/B-4 1974I * KIG (ENOF/B-4 1974

id5

hNUCL1DE

hhe

DECRYHflLFLIFE

12.60

0-B6

GflMMR-RRY TRBLE

Y

S

OECflYYIELD

ORHMR-RHY ENERGY( X ) — G»tOTE« T«0» O. I -

16 Graphical Reptesentation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

fee

Abundance92-50X

2He —-nv0"."863" Li

<o

"""r?û?'"- 2He

JAERI 1280 3. Graphs of Activation Data 17

3|_i TRANSMUTATION CROSS SECTIONS

10"10"3 !0"z 10"'

' NNR (ENOF/B-4 1974' ND (ENOF/B-4 1974• NNP (

101 10* 103 10* 105 106 107 1CPNEUTRON ENERGY ( E V )

I « N2N IENDF/B-4 1974 II • KIB (EMDF/fl-4 1974 I

aLi DECflY GflMMfl-RRY TflBLE

NUCLIDE

h

h

HftLF

LIFE

12.60 Y

0.86 S

0.88 S

6.70E-I7S

DECHY ORMMfi-RBY ENERGY

18 Graphical Repiesentation of Transmutation and Decay Chain Data, Transmutation , . „Cross Section and Delayed Gamma Ray Emission Data J AEK11Z8U

C5

Li

Li

NP

7

fee

!3e

Abundance100.00X

Li

2He ""o:f i Li

to

JAERI 1280 3. Graphs of Activation Data

in0

~

IXQD

^—

to 1 LT*

to

§io-s

icr6

in-7

;B« T R R N S M U T R T I O N CROSS S E C T I O N S: r ;; [1 r :

1

•

10"3 10"2 10"1 10P 10' 102 103

NEUTRON ENERGY IFV:• Nfl IEHDF/e-< 1974

N O cKI2KI lENDF/B-i 1874

" N P I E U D F / B - ' 1 9 7 4• NG l tNDF/B-4 1974• NT (EWDF/B-4 1974

10 4 1 0 s 1O5 1 0 7 1O9

iBe DECflY GnMHn-RflY TRBLE

NUCLIDE

l iLi

'fee"Be

HHLFLIFE

0.86 S

0.88 S

0.18 S

2.50E«06Y

6.70E-I7S

DECflY ORMMfl-RflY ENERGYY I E L D IV.) - H E P T H IHO« 0 . 1 -

5.11E-06

0.00

S-IX-DtSJ.OD

j.eOE.oe

3.00

20 Graphical Representation of Transmutation and Decay Chain Data, Transmutation H F R I I ?snCross Section and Delayed Gamma Ray Emission Data J

Abundance19.807.

JAERI1280 3. Gnphs of Activation Data 21

10 4

1 0 3

1 0 2

.10° _

toera

I1 0"3

i<r«

in-6

TRRNSMUTRTION CROSS SECTIONS! "' ' ' ' '

1

[I "-t^T

r L r ^ s ^ ^

'2\rLz/

r i

i1

"I

10-3 10"2 10"' io° IO1 IO2 10s

NEUTRON ENERGY ( EV)I04 10 5 10 6 107 10P

' Nfl IENOlVa-4 1974' NND IBNL326 1916- NNP IJU-HII-3 U-70

- NP CEUOF/B-4 1*74-NC (- NNR (

sBNUCLIDE

'feehi

DECRYHRLFLIFE

2.50E*

GRMMR-RRY

06Y

6.70E-17S

TRBLEDECRY

YIELDQRHHR-RRY

(7.)ENERGY

C«EHTC« TUMI O . I -

,„ Graphical Representation of Transmutation and Decay Chain Data, Transmutation i A FB i n»n^ Ooss Section and Delayed Gamma Ray Emission Data JAbKii«u

zHe

12

¥JO* DUO/

Abundance80.20/:

c\

JAERI1280 3. Graphs of Activation Data 23

i o-'

10"z _

2

iio-3

- l c r 4 _

toIO

i o - 6 L

Iff1-7

icr3

TRRNSMUTflTION CROSS SECTIONS

i

- i

n

m «

fp •:

•

•

10PNEUTRON ENERGY

103

( EV)10* 10s 10s 107 105

' NR ICNDF/B-4 1974' ND (' KI2N IENDF/B-4 1974

• NP lEtJOF/B-4 1974- KIG (EMOF/B-4 1974• NT (EWDF/fl-4 1974

DECRY GRMMR-RRY TRBLE

NUCLIDE

hMBe'iBe' Bfee

HfiLFLIFE

0-88 S

2.60E-»0SY

13.60 S

0.020 S

6.70E-17S

DECBYYIELD

ORHMfi-RBY ENERGY('/. ) —BREflTER THRU 0<l-

5.I1E.050.00

5.11E-000.00

f-UE»O«99.00

<.44E*D»1 ! »

8.7IE.064.51

5.I5E-D6Z.19

4.67E.0I

i . 00

7.171-06

1.74

6 . 0 H . M

0.47

1.77f<06

o.n

24 Graphical Representation ofTniumutation and Decay Chain Data, Transmutation , . „ , , , a n

Cross Section and Delayed Gamma Ray Emission Data J A t l u 1/<su

A ' '

2He

5L

1 1 -

> NP

1 •*(tM),EC(O.a

'3pz

6

Abundance98.89X

:

JAERI 1280 3. Graph* of Activation Dtta 25

10°

10-' _

z

lio-Vzo

LU

in

to

o

lO'* _

TRRNSMUTRTION CROSS SECTIONS

10'6

„ . . J

! ^ _ I

H f :

1 ^

I

:

10"3 10"2 10"1 10P 101 l t f I t?NEUTRON ENERGY (EVI

10* lCf5 1 0 s 10 7 1 0 s

' NR IENDF/B-4 1974' NO (ENDF/B-4 1S74' KI2N [JU-RI I -3 10-70• NP [JU-Mt-S 1970

• WD I• NT I' NNP I' MNFI IBM.325 1971

DECRY GflnMR-RRY TRBLENUCL1DE

HflLF

LIFE

20.38 11

0.020 S

B.70E-17S

DECBY GflMMfi-RRY ENERGY

Y I E L D ( X ) --HtEOTEK THWI 0 . 1 -

E.1IE.06

0.00

4.44E*DE

] ? >

Gnphical Representation of Trinimutetion and Decay Chain Data, Ttantmutation H C D I n mCron Section and Delayed Gamma Ray Emiitfon Data J u l u u ™

5D * "NIP

"0V025"

Abundance1.117.

12r



10-' _

en

£itrz

-10-3 uLU1/3

Si or*tr

10"b _

icrE I | | ,,,! | | , ,.[.,.,1 1 . f , N J | | | , , ,

10"3 10"2 10P 10' 102 103 10*NEUTRON ENERGY (EV)

105 1L* ] 0 7 1 0 p

' NG I C - 1 Z I N . G I E U D F / S - 4 1 9 7 4 I' Hft I H . D . T . I ] 1 9 7 3 I' M2M I I

' KIP (JHE»I-n-635< 1976 I• NT [ I

eC DECRY GRMMR-RRY TRBLE

NUCLIDEHHLFLIFE

5730

1.60E-I

0.017

Y

06Y

SS.IIE*W

0.00S.Mf.M

7.10

DECBYYIELD

GRMMfi-RRY ENERGY(V.) --C«EHT£« IHW O. I -

28 Graphical Reptesentatica of Transmutation and Decay Chain Data, Transmutation . , . „ . , , . n

Cross Section and Delayed Gamma Ray Emission Data J A W U l / 8 u

14r NP Abundance99-63'/.

csi

12r6L

far

JO P CO

CR

OS

jj S

EC

TIO

N (B

flRN

)O

C)

O

O

O

E J

J J

I I

I I

I |

30 Graphical Representation of Transmutation and Decay Chain Data, Transmutation , . . . . , lan

Cross Section and Delayed Gamma Ray Emission Date JAt.Ki1.t5u

15r

6L

NIP

2VSD5"

"S73

Abundance0.317.

R

0T0Z5"


TRflNSMUTflTION CROSS SECTIONS

10"z 10"l 10° 101 102 103

NEUTRON ENERGY (EV!104 10s

10P !07 I OP

• KID (' N2N (

• KIP (JU-m-3 1910' KJG I

DECRY GRMHR-RRY TRBLE

NUCLIDE

]EB

15

eC

HRLFLIFE

0.020 S

S730 Y

2.50 S

7.16 S

6.11E-060.00

5.HE.060.00

B.ne*oso.oo

DECfiYYIELD

4.««E.06i.2g

6.SM.06M . M

M.tO

l . | ! [ < n

4.11; . in>o*

o . n

GBMHB-RfiY ENERGYtK) --cttottn imu o. i -

1 .UE-Oto.io

oo Graphical Representation ofTransmutation and Decay Chain Data, Transmutation .„.,„.Cross Section and Delayed Gamma Ray Emission Data J AbKl 1 MM

15

Abundance95 .7BX

'et

"fc


16_

10" '1

TRRNSMUTflTION CROSS SECTIOMS

I 0-2 10' IOP i o l id 2 i o 3 IO4

N E U T R O N E N E R G Y ( E V )10s 106 1O1 I OP

• N G' NNH• NT• Nfl• WO

IENDF/B-4 1974IENOF/B-4 1974

IENDF/B-4 1974(ENDF/B-4 197<

" NNP IJU-SR-3 1910• NP IENOF/B-4 1974• NHE3 I

DECRY GFIMMR-RRY TRBLE

NUCL1DEHBLFLIFE

5730 Y

122-0 S

7.13 S

6-11E-06

?00.00

5.11E-05

0.00

6.13E-06

EC.CO

7-l!E«06

4. IS

DECRY

YIELD

J.7SE«D6

0.B9

OflMMFI-RfiY ENERGY

( X ) --C»EOTE« THRU 0 . 1 -

1.7JE-06

0.1D

34 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI 1280

14 B 14

6L "5?fo?"""" 7N

"So

NP AbundanceO.OAV.

JAERI1280 3. Graphs of Activation DaU

10° eO T R n N S h U T f l T I 0 N C R 0 5 5 S E C . T . I 0 N S

10"1 0 " 3 1 0 " 2 1 0 - ' 10P 1 0 1 1 0 2 1 0 3 10* 1 0 s 1 0 6 1Q7 1CP

NEUTRON ENERGY (EV)• NG I

Klfl [ N . D . T . l l 1 9 7 3 • NP I

NUCLIDE

17

DECRYHflLFLIFE

5730

A.n

GRMMR-RRY

i

s6.11E.06

0.00I.1IE

TRBLE

>06

9.002.HE.OS

0.91

DECflYYIELD

GflHMfi-RftY(X)

ENERGYGRERTER THRU D . I -

36 Graphical Repiesentation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamnu Ray Emission Data JAUKI

2 0

Abundance100-OOX

c\

_

16-80



Iff

I0P 10'NEUTRON ENERGY I E V )

' KIG IENDF/D-4 1974' NNR IENOF/B-4 1974• NT (EUOF/B-4 1974• Nfl IENDF/B-4 1974

- ND IEMDF/B-4 1974- NMP IENDF/B-4 1974- NZN (ENOF/B-4 1B74" KIP IEU0F/D-4 1974

DECRY GRMMfl-RRY TRBLE

NUCUDE

IF'h'IF*b

HBLF

LIFE

11.40 S

7.16 S

109.B M

27.20 S

B-llE'05

0.00

6.11E-06

0.00

E.11E-0S

m.eo9-UE*M

0.00

|.63E'O6

100.00

6.13E-06

6B.60

DECBY

YIELD

GBHKR-RBY ENERGY

17.) --C»E«TE« TH«U 0.1-

7.12E-06

4.7J

J.76E.D6

0.19

1.7JE.0B

0.10

1.171*09

•2.13

1.39E«Ot

ts.oo

I.1OE*OS

S.«7

1.<9E«0l

9 . K 1.47

4 .1MOI

o.u

38 Graphical Representation of Tranimutation and Decay Chain Data, Transmutation . , . . . , , B n

Ciou Section and Delayed Gamma Ray Emittion Data JAUKJ IZBU

nNo

Abundance100.00X

21 2 1 M

2Q_lcNe

JAERI 1280 3. Gnphi of Activition Data

1CT

10"3

TRflNSMUTRTION CROSS SECTIONS

10-' 10P 10 1 10 2 103

N E U T R O N ENERGY ( E VI0« 10s 106 107 1GP

' NRNG

• NP• N2N' KI3N

IENDF/B-4 1974(ENOF/B-4 1974IENDF/B-4 1974IENDF/B-4 1974

' KID I• MNP (JU-RR-3 1970' NfJD I' KINR I

NUCLIOE

CSJ

11N0

11N02 1 h l

11N0

DECRY GflMMfl-RRY THBLEHBLF

LIFE

11.00 S

16-03 H

37.60 S

2.60 Y

22.47 S

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n en O CO CO cn m n —i o cn

f

_J

I I

• '

• •

•

7S Gnphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

isflr

Abundance[TT^~] Abundar2oLal 0.13"/

JAERI1280 3. Cnphs of Activation DtU 79

lrf3 *$~

CD

i

LLJ

CO

COCO

o


'•

J

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' NG• NTmm

• NO

I((JU-««-3 ]B-!0

• N2N 1- N N P C H . O . T . I l 1 9 7 3• N P C M . O . T . ] 1 | 9 7 3


NUCL1DE

HRLF

LIFE

12.36

22.00

H

H

s

6

• HE-OS

O.OD

.HE.06

O.OD

1

9

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IB.80

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87.80

3

E

.HE-OS

0.55

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(0.00

DECRY

Y I E L D

3.I7E*OG

11.50

GflHHfl-RRY ENERGY

( '/. ) --CREPTEH THW

6.9IE-0B

11.10

2 m»0E

4.13

i

0 . 1 -

O!E<OB

I-SB

«.|BE.O6

0.33

].««E.O6

0.27

1.02E-D6

0.16

80 Graphical Representation of Transmutation and Decay Chain Data, Transmutation IABBI I tanCross Section and Delayed Gamma Ray Emission Data J A M 1 * i w

45A5r e- 4 5c20LO ""T65.0D""*" 2]OC

Abundonce2.09"/

"1V85H"


in-i "£0 TRRNSMUTRTION CROSS SECTIONS

1 or10"3 10"2 10° 10'

NEUTRON10* ID3

ENERGY ( E V )• NG i• NT I• NS m . o . T . i i• NO i

• N3N (• N2N (' NNP IJU-HR-3 1810• NP IU.D .T .11 1913


NUCLIDE

2cCa42,

19\

leflr

ilk

HRLF

LIFE

165-0 D

12.36 H

1.85 H

22 .00 H

22 .10 M

6.11E-06

O.OD

5.1 IE-OS

0.00

5.11E-05

0.00

S.11E-05

0.00

1-62E-06

16.80

1.J9E-06

99.16

3-19E-0S

87.80

!.B?E«06

9S.6J

3.13E-0B

0.3S

S.10E-05

BO. 00

l.EOE-06

19. Bl

DECflY

YIELD

J.97E-05

11.60

1.13E-06

77. J8

GBMIIR-RfiY ENERGY

[ X ) --GPEPTC IMnn 0 .1 -

5.t<E-15

11.10

1.07E-0B

2-ri t -05

<.13

3.ESE-05

67.85 61.96

1.02E-OB

I.BI

1.16E-06

SB.00

g.ggt-os

0.33

!.15E-0G

"1.19

i.c<;-05

0.J7

7.JEE.05

3B.40

i.ozt-oe

0.1E

E.51E.05

30.74

82 Graphical Repretentation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data J A t l u " B U

_ N P _ _

1TS.0S'*1-dCa

Abundance0 . 0 0 3 Z

20C0 "

D"~22l I

43

JAERI1280 3. Gnptu of Activation D*U S3


DC

ml

irr'

•

1

•

•

ltr2 lo-1 io° IO1 IO2 io3

NEUTRON ENERGY (EVI04 10s 106 I OP

• NG I• NB [JRERl-M-6354 1916

• KI2N (M.D.I.II 1973• NP (

2tLa

NUCLIDE

2(fol4 7C2 IOC

2dCa

*hril<i ^

DECRYHRLFLIFE

4.53

3.41

165.0

5.40

22.30

115.0

GRMMR-RRY TRBLE

D

D

0

M

H

S

6

6

E

G

HE-OS

0.00

HE-OB

COD

1 IE-OS

0.00

UExreo.oa

l

l

3

1

•30E-06

71.00

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6B.S0

.73E»06

B7.B0

.35E-0S

91.40

4.89E<0E

6.83

B.ltE-OS

BO.00

3.70E-DE

2B.42

DECRY

Y I E L D

B.D8E*DS

6.83

3.I7E-0S

11.CO

3.D?E-06

8 . BO

GRHMfi-RRY(•/. 1

7.67E-0S

o.eo

S.14E<0t

11.10

2.27E<0t

9.EB

2

1

ENERGYGREOTER THBW

.21E-06

4.13

.IBE'OG

8.4]

I .

1 .

0 . 1 -

07E-M

1.B9

B7E-O6

4.7B

J.BBE.OB

0.33

1.44E-.0G

1.B4E-01

0.21

1.02E-.0S

0.1B

84 Graphical Representation of Transmutation and Decay Chain Data, Transmutation , . „ „ . . , « *Crou Section and Delayed Gamma Ray Emiuion Data A t l u * " "

^r R - 49 4920LO B V S W " * * 2IOC •-""•5"r.S0~M"~~ 221 I

4

19NP Abundance

0.19Z

B - c B T •T."53tJ"""* 210C T.'iVS'"" 221 I

8-• • — r r s o


T R H N 5 M U T R T I 0 N C R 0 S 5 S E C T I 0 N S

10"3 1 0"2 10'1-1 10P 101 102 103

N E U T R O N E N E R G Y IEV)

104

• NG (• NT (• NO I

' W2M I N . 0 . T . I 1 1 9 7 3KIP (

20L0

NUCLIDE

2tfol19C2lOC47

47

4 7

ilk

DECRY GRMMR-RRY TRBLEHRLF

LJFE

8.80 11

57.50 M

17.50 S

4.53 D

3.44 D

115.0 S

6.80 S

E.il£«05

0.00

5.J1E'O5

0.0D

5.1!E-05

0.00

5. DIE-OS

O.OO

S.I IE«05

O.OD

G.11E4D5

0.00

E.11E<OE

0.00

3.0BE'06

92.10

4.07E406

7.01

2.01E>06

100-00

1.JOf.OO

77.00

1.59E«0B

L SB.60

1.3SE.0G

91.40

9.S3E*0E

eo.oo

S.86E<05

(S.OD

4.C9E-OJ

6.S3

3.70E-O6

2B.4?

7.B0E<OS

31.19

DECRY

Y I E L D

1.41E-06

0.63

5.65E-05

15.00t.OOE.05

6.S3

3.02E>OE

9.SO

6.1BE.0S

17.37

GflHMfl-RRY ENERGY

( V. ) --CREOTER

2.37E»06

0.48

4.14E-06

0.22

7 .»7E«05

0.20

2.27E«0E

8.SB

2.70E«06

16.U

1.78E+D6

B.4I

1 .S4E.D5

IS.IB

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2.23E'0E

0.20

1.61E.0B

4.76

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0.13

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2.92

1.52E.06

13.07

l.J4E»0B

0.11

J.SK.Dt

10.9B

7.93E<0E

9.92

86 Graphical Representation of Transmutation and Decay Chain Data, Transmutation l AFRI12R0Cross Section and Delayed Gamma Ray Emission Data

4V221 I

IMP221 I

Abundance8.20'/.

CM

45T-22 I I

4 4

2i5 c •••4 4 T -22! I

JAER] 1280 3. Graphs of Activation Data 87

101 zzTi TRRNSMUTRTION CROSS SECTIONS

10'

• NG I T1-NHT (M .G l ENDF/B-4 1974 I' UP (ENOF/B-4 1974 I' KIH UBERI-n-6351 1976 I' N2N (RNL-75-34 1975 1

NNPKI3NNT

221 1

NL'CLIDE

2iSc

22Ti

22Ti

21§C

DECRY GflMMR-RRY TRBLEHRLFLIFE

63.BO D

3-08 H

48.20 Y

3.92 H

2 . 4 4 D

DECRY GflMMfi-RRY ENERGY

Y I E L D < / ! ) —CREOTER THOU 0 . 1 -

6.]1E«OE

0.00

S.J1E-06

172.00

5.HE«05

O.OO

5 . H E - 0 5

IBB.00

E.llE'Ot

0.00

8-B9E«06

100.00

1.?0E-0E

0.1S

1.B4E-04

K.tl

1.18E.D6

M.BI

].OOE.OS

1.60

1.12E.O6

100.on

S.7(E<04

Bt.00

1.50E.OB

0.91

1.J3E.01

L S I

I.45E-05

0.40

J.BBt-08

0-11

I.JH-OB

l . U

88 Graphical Representation of Transmutation and Decay Chain Data, Transmutation J AERI1280Cross Secdon and Delayed Gamma Ray Emission Data

22 I I

47c21OC

NP

•-3-.4-2D"""22 I I

Abundance7.4 0V.

2iSc 83M

45T-22 I I

4r

JAERI1280 3. Giaphs of Activation Data

10i 2"T; TR R N S M U T R T I O N CROSS SECTIONS

10-10"3 10° 101 102 103

NEUTRON ENERGY (EV!10s

• NG ( Tl-HRT (N.G1 ENDF/B-< 1974 I• NP tCHOF/B-4 197-4 )• NR (JU-RR-3 1910 I

• N2N URERI-H-6354 1976• NNP 1BUL32S 1976• N3N t

22Ti DECRY GflMMR-RflY TQBLE

NUCLIDE

47

21OC

2iSc

22 1 1

HRLF

LIFE

3.42 D

83.80 D

3.08 H

DECfiY OflMMfl-lffiY ENERCV

Y I E L D (7.) --CBEBTER IHBU 0 . 1 -

S.IIE'OS

O.uO

6.I1E-06

0.00

5.UE.0S

172.00

1 -E9E.05

68 .SO

B-89E-06

100.00

7.SOE-05

0-15

1.12E-06

100.00


4 9 T -221 I

o

22 I IAbundance13.107.

C\l

4 7 T-221 I

4 6 T-22 I I

JAE1U1280 3. Graphs of Activation Data

101 TRflNSMUTRTION CROSS SECTIONS

10"z 10"' 10° 10 ' 10* 103

NEUTRON ENERGY ( E V )10* 1 0 5 ltf>

KG I Tl-NHT IM.G1 ENDF/B-4 1974 1HP 1EN0F/B-4 1974 I

• NR I N . O . T . l l 1973 1• N2N [JU-tlR-3 1970 1

• NNP IDUL3ZS 1976• KI3N I

107 108

2gTi DECRY GRMM.fl-RRY TRBLE

NUCLIDE

2^Ca

2lSc

HRLFLIFE

43 .67 H

165-0 D

3.« 0

B-llE'060-00

5.J1E.050.00

3.B3E-0E100.00

1.S8E-0569.60

I.3IE-0B100.00

DECflY

Y I E L D

1-04E«06

97.60

GRMHR-RRY ENERGYV.) — GRCnTEH THRW O. I -

1.7SE«05

7.47

I.J1E'O6

2.38

92 Gnphical Repiesentation of Transmutation and Decay Chain Data, Transmutation IAER11280Cross Section and Delayed Gamma Ray Emission Data

so22 I I

22 I IAbundance

5 - 4 0 *

48221 I

CO

V221 I

JAERI1280 3. Gnphs of Activation Data

10- TRflNSMUTRTION CROSS SECTIONS

10"10"3 1CT? 10"'10° 101 102

NEUTRON ENERGY103

[EV:• NG ( TI-NBT (KI.GI ENDF/S-4 1974 )• NP (BNL32S 1976 I' NR (JBERI-M-6364 I97E )

' KIZN >jnEni-n-63S4 1976' KINP (BNL3Z5 197E' N3N I


NUCL1DE

ziSc4821OC

HflLFLIFE

57.00 M

O.67 H

DECflY GBMMfl-RflY ENERGY

Y I E L D IV.) — WttPTEK 1HPU 0 . 1 -

S.11E*!*

O.OD

6.11E-05

O.OD

».»?E»nE

100.00

1.31E-O5

1OD.00

1 -0<E-05

97.50

1.76E-0B

7.47

1 J1E-06

94 Graphical Repiesentation of Transmutation and ficcay Chain Data, Transmutation JAERI1280Cross Section and Delayed Gamma Ray Emission Data J M . ™ I M

NP

:I

51 B_ 51221 I 5".~8D'tf~"~~ 23V

221 IAbundonce5.20'/

49C E21DC —"F7.

49" * 2222 I I

22 I I

?cCo —4-.-I4" 2iSc 22T1

3. Graphs of Activation Data 95

10

icricr3


10'1-2 10"1 i d° IO1 IO 2 io 3

NEUTRON ENERGY (EV:104 10s I07 106

• NG I TI-UflT IN.G1 ENOF/B-4 IS74 )' NP ( N . 0 - T . I 1 1973 )' Nf i (N.D.T-11 :973 1

• N2W l j nE» l - r ! - 6354 1976• NNP I• N3N (

22Ti DECRY GRNMR-RRY TRBLE

NUCLIDE

22li50

21OC

20C0

2lSc

2iSc

HRLF

LIFE

5

1

4

3

57

8C

71

54

42

.00

f1

H

D

3

M

5

S

5

5

E

•IIE'OS

0.00

.!1E'O5

0.00

• HE.05

0.00

.]1E«O5

0.00

.1IE«O5

O.DO

3.19E»D5

93.<0

1.55E.06

100.00

1 .30E-06

77.00

1.59E+D5

68.60

DECRY GRMMR-RRY ENERGY

Y I E L D (Y.) --WEOTtR 1MON 0 . 1 -

9.?7E'055.41

1.12E-06

9B.04

4.B9E*0S

6.63

S.OeE'05

1-26

5.?3E.0S

66.27

8.0BE-05

6-«3

7.67E-05

0.20

96 Graphical Representation of TiansmuUtion and Decay Chain Data, TiansmutationCross Section and Delayed Gamma Ray Emission Data

MERI1280

5 1 \ /23V

5022 I I

NP23

Abundance0-25/:

422

423'

4 7 C21OC

B-22 1 I


101 23V TRANSMUTATION CROSS SECTIONS

10"3 1 0 ' 2 10"1 1QP 101 10* 10 3 10* 10 s 10 6 107 103

NEUTRON ENERGY (EV)' NG ! U-KlflT I N . C ) E M G F / S - 4 1 9 7 4 I' KIP I N . O . T . l l 1 9 1 3 I

• WZM (H.D.T.II 1973• NP (

23V DECRY GRMMR-RRY TRBLE

NUCL1DE1721OC

2 V

HRLFLIFE

3.12

327.0

D

0

S.31E*O5

O.OD

1.S9E-05

68.50

DECRY

Y I E L D

GftMMR-RRY ENERGY

( V. } --C.PEOTER THflH 0 . 1 -

Gnphical Repiesentation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

231/

Abundonce99 .75X

21iSc — 57 :Bnn PC"*22 i i4

23

4821OC — 4"

4 8 T '221 I


zaV TRRNSMUTflTION CROSS SECTIONS

' NG ( V-WHT (W.DJ EWOF/8-4 J974• NP I V-NUT (N.P1 ENDF/B-4 1974• Nfi [ U-NBT I N . HI ENDF/B-J 1914

I8NL32S 1S761 M2N I U-NBT [N.2N1 ENDF/B-4 !97<

M3KJKIDNKIPK1HE3 I

I V-MRT (N.D) ENOF/B-4 1914 I

23V

NUCLIDE551

5122T1182lOC47

23V19

ziSc

DECRY GRMMfl-HPILFLIFE

3.76 H

5-80 ti

43.67 H

3.42 D

327.0 D

57 .00 rt

5.11E«05

0.00

6.1 IE-OS

0.00

5.11E-05

0.00

S.11E«05

0-00

5.HE.OB

0.00

?RY TflBLE

1.43E*06

100.00

3.19E-06

93.40

S.J3E-05

100.00

1.59E-0S

68.60

1.33E«06

0.59

9.27E-05

8.41

J.31E-06

10D.OO

• ECflY

Y I E L D

1.S3E-06

0-12

6.O8E-06

1.25

1.04E-D6

97-50

GflMMfl-RRY ENERGYV. ) --GRERTER THRU 0 . 1 -

1.15E.05

7.47

1.21E-D6

2.35


5 1 w EC 51

23V —"r / r

523

KIP 5a. Abundance4 .35 / :

4 9 T-221 I "327T0D"423sV 24Cr

23IJ --,-, '6R-48

22l


10

101

TRRNSHUTflTION CROSS SECTIONS

10"3 10-2 10"' 10P 1 0 l 10 2 10 3

N E U T R O N E N E R G Y I E V )10* 10s 106

* NG I CR-HRT IN.G) EWDF/B-4 1974 1• N2N I HNl-75-34 1975 1' N3N I I• NP I KFK-25B6 1971 1

' NO I• NT t' MR I KFK-23S6 1177' NNP I U . D . T . l l 1973

NUCL1DE

2-Cr

A 8

23V

23V

DECRY GflMMfl-HflLF

LIFE

27 .70 D

<1.90 M

21 .56 H

327 .0 D

1S.9B D

5.I1E-05

0.00

5.11E.0B

200.00

5.11E-05

0.00

B.HE.06

200.00

RRY TRBLE

3.J0E>0S

10.20

I.OGE-04

SI .00

3.05E-05

99.42

1.S3E-O6

29.29

.'•16E-05

94.55

!.»3E«0E

I0O.OO

).31E'0t

S7.50

DECPY

Y I E L D

6.23E-04

15.64

S.44E.DS

7.76

BftMHB-RflY ENERGY

[ V, i --CREBTER THOU 0 . 1 -

2.?<E.0t

2.41

9.7«E»0S

0.77

B.OiE.DB

D.1S

1.44E«06

0.12

102 Graphical Representation of Transmutation and Decay Chain Data, Transmutation IAFQI nanCross Section anl Delayed Gamnu Ray Emission Data 'AtK1 l ™"

53

52 .23V

5123V

N P |52 | AbundanceRI | 2 4 L r | 8 3 - 7 9 %

CM2

51

50

4 9 T -221 I

JAERI1280 3. Graphs of Activation DaU 103

52

IO1 M TRRNSMUTRTION CROSS SECTIONS

10"10" 10"* 10"1 10° 101 10* 103

NEUTRON ENERGY IEV]• N2N ( filJL-75-34 1975 I' N3N I 1• NG ( CR-NBT IN.GI ENOF/B-J 1914 1• NF I KFK-2386 1977 I

105 I06 107

• ND I• NR [ KFK-2386 1977• K1WP I

C DECRY GRMMfl-RRY TRBLE

NUCL1DEHRLFLJFE

27.70 0

3.76 M

S.llE'050.00

6.11E-060.00

3.20E»0510.20

I.OE-06100.00

1.3JE.O60.59

DECRY

YJELO

1.S3E*0E

0.12

GRHHfl-RRY ENERGY1'/.) --CREOTER THQU 0 . 1 -

Graphical Representation of Transmutation and Decay Chain Data, Transmutation IAPCI I 7Rf)Cross Section and Debyed Gamma Ray Emission Data

5

523

523

NP trAbundance9.50Z

"27:"5 1

22 I

JAERU280 3. Graphs of Activation Data

l O

lO" 4

1011-3


1 0 " 2 10" 1 10° 10' 102 103

NEUTRON ENERGY ( EV!

10* 10 7 ICP

' N2N I KFK-Z3B6 1977 I• N3N I I' NC I CR-HBT IN.O) EUDF/B-4 1J74 I• NP I KFK-23B6 1971 1

" m I KFK-2366 1977• MNP ( JU-RR-3 1970• KIHE3 I

53

24Lr

NUCLIDE

51

&

S[

2211

:ECRY GRMMR-HALF

LIFE

27 .70 D

1.60 M

3.76 M

5.80 M

e.HE'OS

0.00

5.!!E«05

0.00

5.I1E-05

0.00

S.11E-05

0.00

?RY TRBLE

3.20E»05

10.20

S.E4E*06

90.00

l.i3E*06

100.00

5.HE-05

99.40

DECRY

Y I E L D

GRMMfi-RRY ENERGY

( V, ) --PREflTER THBH 0 . 1 -

1.S9E-0E

1.01

1.3SE-0E

0.50

S-J7E-05

8.41

J.S3E-05

0.77

1.53E-06

0.12

«.oo;.05

1.25

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0.39

2.17E.05

0.16

5.31C.0S

o.ie


tlv

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52r


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N E U T R O N E N E R G Y I E V )

104

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1 WP I KFK-33BE 1917• W D (• NB [ KFK-23B6 1911

5 4

NUCL1DE

23V

22Ti55_•2<Lr

DECRY GRMMR-HflLFLIFE

1.6O n

5.80 M

3.52 «

43.00 S

6 .HE.05

0.00

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S.IIE'OS

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3.19E.05

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5.41

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100.00

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ti.to

DECfiYYIELD

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0.71

6.08E-05

l.?5

t.ncm60.00

GflMMfl-RfiY ENERGYt'/C) --CSEOTEII THRU 0 . 1 -

4.4SE.05

0.39

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o.ie5-31E.05

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1 .»!-tm4.»0

108 Gnphical Representation of Transmutation and Decay Chain DaU, TiansmuUtion • APRI I 9R(1Ooss Section and Delayed Gamma Ray Emission DaU J A I l l u " o u

5 2

!H 56cr' " " - 26i~e

55 NP Abundance100.00Z

523

53,T.60"M'


10"" r.

10"


10"3 10"2 10"110° 10' 10* 103

NEUTRON ENERGY (EVi104 105

" NG I ENDF/B-4 1974" NP ( ENDF/6-4 1974- N2N ( ENOF/B-J JB74' MNP I EHDF/6-4 1974- Nfi ( ENDF/B-4 1974

-N3N I- ND ( EHOF/B-4 1974• NT (•NNT (- KIHE3 ( ENDF/B-4 1874

107 109


NUCLIDE

55

2-Cr

23V

2H

HW.FLIFE

2.58 H

3.52 M

312.2 0

3.76 M

3.7«*06Y

1.60 M

e.nE*os0.00

5.1IE-O50.00

DECfiYYIELD

».«7E»06C8.81

i.giE'OtJ7.?7

J-IIE'06I4.3S

«.3S£.O5100.00

CRMMfi-RBY ENERGYIV.) —OtCnTEK THOU O. l -

Z.E2E<0S

0.99

2.66E»06

0.66

2.B6E«0»

0.31

3-57E-0E

0.17


JAERI1280

55.

54

55_

Abundonce5.80X

23V

50


10 T R f l N S M U T f l T I 0 N C R 0 S 5 S E C T I 0 N 5

Iff10"3 Iff"1 10° 10l

NEUTRON

• NC• N P• KIR• KI2N• K I 3 N• KID

FE-NPT IN.GI EUDF/B-4 1974ENOF/B-4 1974KFK-2366 1977flNL-75-34 1975

3YKIT.KIT"KIKIPKIKIRKIHE3

103

( E V )1 U.D.T1 U.D.T1 U.D.T

.11

.11

.11

104

197319731973

26Fe

NUCL1DE

2ih

IK2?e52_

3ft.

DECRY GRMMR-HflLF

LIFE

2.69 Y

312.2 D

27.70 D

8.51 H

3.74E*06Y

2.51 ti

8.27 H

21.10 M

S.S9 D

=?RY TRBLEDECfiY

Y I E L D

GRMHR-RBY ENERGY

i'/.i — CREOTER THDH 0 . 1 -

5.lit-05

195.00

9.7«E>0S

42.00

t.Z7C»0>

st.ts

2.7St*0«

14.47

i .ejt-OB

0.51

E.Uf.OE

O.00

S.llE'OE

114.00

5.11E-W

I9S.S0

E.llE'OS

E7.00

I.OlEtOS

9B.U

1.E9E«0E

99.20

1.43E»0B

88.27

1.43E*0E

100.00

1.33E<0(

•S.60

3.7BE-0S

1.6B

9.3EE*0S

. 94.SO

l.0IE>0(

St.71

1 -73E'O6

O.ZZ

7.44E*0S

90.00

!.3<E«Dt

13.02

I.71E.0S

1.29

1.3SE-O6

5.07

1-26E.C6

4-J1

5.4BE.0S

3.3?

9.46E-06

0.9S

6.41E-0B

0.40

6.00E.06

0.39


JAERI1280

57

Abundance91 -80X

53

54^ 6


IO TRRNSMUTRTION CROSS SECTIONS

10"3 10"2 10"1 10° 101 I02 103

NEUTRON ENERGY (EV110* 10s 107 109

• NP [ ENDF/B-4 1374 )• N2N I N . D . T . U 1973 )• N3N ( I' NG I FE-NRT IN.GI ENOF/B-4 1971 )

• ND I' Mfl ( rFIC-Z386 1977' NKIP I BNL-325 1816' WMR I

2 ere

NUCLIDE

Ihn

DECRYHBLFLIFE

2.56

2 .69

GRMMfl-RRY

H

Y

TRBLEDECAY

Y I E L D

DRMMR-RflY ENERGY

( '/.) — GREflTEK THRU 0 . 1 -

Gnphical Representation of Tnuumutation and Decay Chain Data, Transmutation , . . „ , . - f i n

Cross Section and Delayed Gamma Ray Emission Data J A f c l u LMU

?6FeAbundance2.15Z

zlin -—2- . I !

54

JAERI1280 3. Graphs of Activation Data

101 TRRNSnUTRTIQN CROSS SECTIONS

CD

UJ

to 10-2L

o

io-4

I I

icr3 1CP 10 ' I t ? ! 0 3

NEUTRON ENERGY ( E V )10s 106 107

N2NN3NNGNP

l(( FE-N(!T (U.O1 ENOF/B-J 19I B-FK-2386 1977

1]

74 ]1

• ND (- KIR ( KFK-2386 1971" NWP I H . D . T . I I 1 9 7 3

2eFe DECRY GRMMR-RRY TRBLE

NUCL1DE

2H

HRLF

LIFE

2.69 Y

1 -54 M

2.58 H

DECRY

Y I E L D

GRMHR-RRY ENERGY

r'/. ] --CREnTCR THPH 0 . 1 -

E.I IE-OS

0.00

I.22E-06

10.30

6.92E-06

4.0S

3-S2E-05

1.55

1.3EE-05

1.43

1.61E-D6

0.5S

6.70E-OE

0.393.67E-DE

0.30

1.J6E-0B

O.?4

8.71€-06

0.19

116 Graphical Representation of Transmutation and Decay Chain Data, Transmutation JAERI 1280Cross Section and Delayed Gamna Ray Emission Data

594"4".S~6D"~"~ 2 C 0

NP

••65 ".SOB"

5§_ 1 Abundance0-29"/

2 re

552*1 2=1 in


sa_101 *T« TRRNSMUTRTIQN CROSS SECT IONS

l or10"3 10-' 10° 101 102 I03

NEUTRON ENERGY (EV]10"

' NG I ENDF/0-4 I97<" W2N (

- WP- MR

I KFK-23B6 1977I U.O.T.IJ 1973

DECRY GFIMMR-RRY TRBLE

NUCLIDE

5a_

55

?Cr

HfiLFLIFE

44.56 D

6 5 . 3 0 S

3.52 M

6-HE-05

0.00

6.UE-05

0-OD

1-I0E-D6

66.60

8-1IE-06

62.20

I .Z>E*06

13.60

1.3JE-0B

5S.II

DECRY

Y I E L D

l-9JE»06

2.66

<-69E-06

I9.9S

GFIMMR-RRY ENERGY

( X ) —GRERTtR TM H O. l -

1 .OE'OS

0.B7

S.61E-05

13.01

3.35E'0S

0.17

1.67E-06

io.es1.J7E.06 '

6.47

6.t<E-06 I.77E«0t

2-85

1.7BE-06

2.66

us Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

60 m.

2-7L0

60-2C0

" - * . 6" • - 2

Abundance100.007.

CM

zsHn •2V5B1H"

JAERI 1280 3. Gnphs of Activation Data 119

59.ID2 gCo TRRNSMUTRTION CROSS SECTIONS

10"10"3 10"2 10"1

' NG [ ENDF/B-4 1914' NR ( ENDF/B-4 191<

IO1 IO2 io3

NEUTRON ENERGY IEV)

104 10s 10* 1 0 7 I OP

' KI2KI I ENDF/B-1 1974


NUCLIDE60—

thn56_2C060m.

2C0

HRLFLIFE

5.27 Y

2.58 H

70 .78 D

10.47 M

B.llE'05

0.00

5.11E-05

90.00

B.MC-OS

0-00

I.17E-06

100.00

8.1 IE-OS

99.44

3.S0E-04

2.00

1.33E<OB

100.DO

g.C4E>05

0.14

I.35E-0B

0.24

DECRY

Y I E L D

1.67E«D6

0-64

GfiMMfi-RRY ENERGY

(V.) — CREHTEd THRM 0 . 1 -

120 Graphical Representation of Transmutation and Decay Chain Data, Transmutation IAEBI i n nCross Section and Delayed Gamma Ray Emission Data JAUKI i « w

Abundance68-30Z

SEU27UT

en

28Nl

JAERI1280 3. Gnphs of Activition Dalm 121

TRf lNSMUTRTION CROSS S E C T I O N S

icrB

10" 3 10" z 10"'1GP 101 10* 10 3

NEUTRON ENERGY I E V' N2N

• KIP"• N N P• KI3N

NG

ENOF/B-4 1974ENOF/B-* 1974EUDF/B-4 19746NL325 197S

Nl-NDT (N.O) EHDF/B-4 1971

• KID• KIT- Nfl- WNfi- KIHE3

U . O . T . l l 1979

KFK-I3B6 1977BULSZS 197S

DECRY GflMMR-RRY TRBLENUCL10E

2C058p

58m

27tO

lh\lh\5b

HRLF

LIFE

35-99 H

271-6 D

70.78 D

9.15 H

6.10 0

7.SOE+04Y

78.76 D

2-69 Y

5.11E«05

SO. 00

6-1 IE-OS

0.00

5.11E-05

90.00

5-IlE«05

O.00

6.11E.06

0.00

1.3BE»06

77.60

1 .J2E-0B

65.60

t.HE-0598.44

1 -taoos

9B.B0

1.92E.06

14-C9

1.36E.06

H.I7

B.6<E-05

0.74

a.UE.Dt

74. IE

DECftY

YIELD

1.?7E*05

It.90

l-44E»04

8.76

I-B7E-06

0.S4

7-BOE»05

47.»S

GBHMfi-RBY ENERGY

(' / ) — GREOTEH

1 -7BE<0B

7.13

6.92E-06

0.1B

; . t iE<0 (

34. D]

«.tOE*0B

SI . U

«ni 0.1-

1.6IE-O6

15.11

B.II£»DS

40.00

«.<7E*0B

SS.S5

1.24E.0«

17.(7

I.I0E»06

16.8!

1.77E*0t

IB.B9

1.04E.0i

13.99

2.03E<0l

7.89

3.2SE<Dt

7.41

1.3iE<Oi

4.33

t.taun

3.DB

122 Gnphical Representation of Transmutation and Decay Chain Data, TnnsmutationCross Section and Delayed Gamma Ray Emission Data JAERI12B0

28N!

Abundance26-1 OX

c\

SB


IO1

10P _

SlO"1

ccCD

ntrz _

Sio-3LIDCOO

(_) J U _

10"5 _


10"E

• 1

H

j

-

• :

icr3 iO"2 10-'10P 10 ' 10* 10 3

NEUTRON ENERGY I E V !10* 10s 10s

' N P n• NP n

• N2N• N3N•NB

1 EHDF/B-4 1974 )I ENOF/B-4 1974 1( KI.O.T.ll 1973 11 )( NI-NflT (N.OI ENOF/B-4 1974 I

• NO I• KIR I KFK-23B6 1977' MMr ( BNL325 1976• W H E 3 I

!07 I OP

DECRY GRMnn-RRY TflBLE

NUCL1DE

CO

2TC0

BOR

5 a , .

HflLF

LIFE

5.2T

10.47

7.50E.C

Y

(1

MY

5

6

.IIE'OS

0.00.HE-06

0.00

1.17E*DE

100.005.«OE-0<

?.oo

1-39E'0E

100.DO

1.99E*0C0.24

OECflY

YIELD

cnnnn-pnY ENERGY

V/A —CREflTER THRM 0 . 1 -

124 Gnphical Representation of Traiumutttion and Decay Chain Data, TiansmutationCrow Section and Delayed Ganuna Ray Emiuion Data JAERI1280

Abundance1 -137.

2 CO* 60M>" 28INI

JAERI 1280 3. Graphs of Activation D»t« 125

10

10"


10-3 10-2 10P 10l ID2 103

NEUTRON ENERGY (EV110* 10s 1 0 7 ICP

• NP I JU-HR-3 1970 I• KI2N I KFK-2386 1977 I' N 3 N ( I' NG t M-NHT (N.G1 EHDP/a-4 1974 I

' KID I' NR I KFK-J386 1977' NMP ( M.O.T.ll 1973

DECRY GRMhR-RRY TRBLE

NUCLIDE

2-Co

2 ^ 0

HflLFLIFE

1.65

S.27

10.41

7.SOE<

H

T

11

06/

fi.

6 .

5.

IIE'060.00HE-OSO.OO

HE-05

O.OO

56.00

1.17E.08

100.00

5.90E*D4

3.011.5SE.06

100.00

1.53E-0S

0.S1

DECRYYIELD

O-GO

GRMMfi-RRY

('/.)

ENERGY

GRERTCIt THRU 0 . 1 -

126 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data I*PRI nan

2eNi

61V65H"

Abundance3.59X

5V

JAERI 1280 3. Graphs ot Activation Data 127

101 26§Mi TRRNSMUTRTION CROSS SECTIONS

ICT10° 101

NEUTRON• NP- I JU-ltR-3 1910• NPn ( K.O.T.t1 1973• Nfl ( JU-RR-3 1970• N2N I KFK-2386 1977

ENERGY• N3N• NG• NNP

I NI-NBT (N.DI ENDF/B-4 1974 1I I I .0 .7 .11 1173 1

62L |

NUCL1DE

ZTCO62m

2C0

2iFe

2-£0

2^li

DECRY GRMMfl-RRY TRBLEHRLF

LIFE

1.50 n

13-91 M

4 4 . 5 6 D

l.BS H

100.1 Y

6-I1E.06

0.00

6.I1E-06

0.00

S.I1E-0S

O.OO

s.nt-05

0.00

l.nE-06

82.60

1. HE-OS

97.90

1.10E-06

se.so5.1IE.D4

K.OO

2.30E«06

16.97

1.16E-06

69.04

1.2»E»06

45.50

t.OIC-Ot

9-02

DECRY

YIELD

I.13E«OS

IS.64

J.OOE-Dt

19.59

1 .B2E*0S

:.es

(•4IE-0B

o.co

ORHHfl-RRY ENERGY

m1-SBE'OB

2.36

1-12E-06

7.00

1-43E.05

0.97

—C»tOTE« IHOH 0 . 1 -

J.3EE-06

1.11

: . IOE*OB

6.92

3.35E.05

O.!7

3.IBE.06

0.B4

7.7BE.05

J.OD

I.<9E'O6O.<4

?.30E-0S

1.78

3.37E-O8

0.43

B.16E-0B

1.39

3.27E<06

0.29

1.13E-06

1.39

128 Graphical Repiesentation of Transmutation and Decay Chain Data, Transmutation IAPRI UROCross Section and Delayed Gamma Ray Emission Data I M I U

2eNi6 5 r

" " - 29LU

6Nl

-.fe-—

Abundance0 .9 1 7.

3- 63TOD. i r " * 29Cu

ro

2a\ii

61

2B- 6 1 K I .

1Y65H""- 28NI


]Oi

10° _

l i tr1

TRflNSMUTPTION CROSS SECTIONS

10"2L

Sicr3

ce;u)

10"" _

10"

;

-i-mn,- . i IIIIII|- i r.niTT, r-

N ...

ii-nn, • .

•J'L

< I M M | 1 I-TTHI|- -i i-rii-m;

f !\:;

10"3 10° 10' 102 103

NEUTRON ENERGY (EV)104 1 0 s 106 107 10P

- NG I Ul-NRT IN.G) ENDF/0-4 1974 I' N2N I N .D .T . l l 1973 I• N3N 1 1• NP I KFK-2306 1977 1

- NO I• Wfl ( H . 0 . T . I 1 1973• NNP I N . D . T . l l 1973

DECRY GRIihR- TRBLE

NUCLIDE

6V2X-0

2 ^ 061—

HRLFLIFE

2.52

100-1

0.30

27.SO

5.98

1 .65

H

T

S

S

M

H

5

5

.HE'05O.OO

.11E-O5

O.OO

S.I1E-05

5

S

O.OO

. H E . 0 5

0.00

.JJE'DS

0.00

1

1

8

1

E

.<6E*06

23.60

.35E-06

10.00

.71E«04

49.30

.;IE*OE

43.60

.71E«04

8G.00

J-1JE-0B

15.19

9.31E-05

5.00

i.tll'Ot

t.B4

1.D3E.06

42.SE

9.09E.05

3.02

DECRV

YIELD

s.fet'05

4.76

1.501-05

1-76

I.3BC-06

22.42

J.42E.DB

O.EO

GRHHB-RRY(Y.)

1.6ZE»0B

0.49

1

1.07E-OB

l.SE

1.SSE<OE

7.01

9

1

ENERGY

CRERTCR THBN

.72E»D6

0.40

6

.17E«05

1.J7

.J0E.D5

6.36

e

2

0 . 1 -

OBE'OB

0.30

14E.0S

0.4E

01E<0G

4.44

6.09E'06

0-16

l.7BE«0B

2.0J

E.ItEÔE

0.99

7.48E«0B

0.8]

130 Graphical Representation of Transmutation and Decay Chain Data, Transmutation J AERI1280Cross Section and Delayed Gamma Ray Emission Data

Abundance6 9 . 2 0 X

CM

?eNi-*««*««'"-- 2£u


JijCu TRf lNSMUTRTI0N(:R05s SECTI0NS

1 Cr3 10" 2 10"1 IQP 1O1 10 2 JO3

N E U T R O N E N E R G Y ( E V )- NG• N2N' N R »- N f i n

• N3N• NP

CU-NRT IKI.GI EUOF/B-4 1914 )JU-RR-3 1970 IENOF/B-4 1974 IENOF/B-4 1914 1

N . D . T . l l 1 9 7 3

' KIO I• NT (• NNP I BN1325 1976' KINFI I' NHE3 I N .D . I . 11 1973

29LU

NUCLIDE

?sCu6 2 r2<D)

2C060m

2 CO61_29U1

lh\2TCO

DECRY GRMMR-HflLF

LIFE

12.70 H

9.73 M

S.27 Y

10. *1 M

3.41 H

100.1 Y

; .6S H

^RY TRBLEDECBY DRMHR-RflY ENERGY

YIELD m -CREOTER mnu o.i-

5.11E«05

St.OD

6.I1E.06

I9E.O0

6.HE-05

0.00

S.1IE.05

0.00

E.11E.06

0.00

1-36E«06

O.EO

1.17E.06

0.36

1.17E-0B

100.00

8.I0I.04

Z.DO

2.B«E»0B

13.20

6.7BE.06

O.IG

1-55E.06

100.00

1.39E-0S

0.24

S.EBE.Ot

•11.79

S.7IE*04

t.n

1.11E.01

4.92

3.73E.05

2.94

* .0K<OI

1.21

S.I9E<0t

1.2B

1.21E.0S

o.to

t.iiora

0.45

B.llE'DG

0.00

t.71E*04

K.00

S.OBE'Ot

3.02

8.42E*0S

o.eo

132 Graphical Repiaentation of Transmutation and Decay Chain Data, Transmutation j AF.RI 1280Crou Section and Delayed Gamma Ray EmitiioR Data

*6j- B- 6 S29LU — " S'.TOff" — 302LD

65,dCu

Abundonce30.80X

OJ


65,101 z£u TRflNSMUTflTION CROSS SECTIONS

1CTI0P 10'

NEUTRON• NG I CU-HBT (N.O) ENOF/B-4 1974• N2N ( ENDF/B-4 1974' KINfi I BWL32B 1976' KIP I ENOF/B-4 1974- Nfl ( ENDF/B-4 1974

IffENERGY

- KI3KI l- KID (• N T I- N N P I euiSZS 1*76

29Cll

NUCLIDE

2stu

2dCu

2'to

2-Co

DECRY GfiMMfl-RRY TRBLEHOLF

LIFE

5.10 n

12.70 H

1.65 H

2.52 H

13.91 M

1.50 M

100.0 Y

B.llE'OB

O.OD

6.UE.06

38.00

B.11E.05

O.OD

».nt-t»0.00

t.HE«060.00

6 . H E . OS

O.OD

1.04E«06

8.00

1.3BE-06

0.60

•.71E-04

86.00

).48E«0«

a.aI.17E»O6

•7.10

1.17E.06

a .so

0.33E*0S0.14

9.0IE-059.0?

1.12E*0Bis.ig

l.liEtOtU.D4

J.30E.Ot15.17

OECflYYIELD

t.»E»DS

O.EO

3.nr*os4.7t

I.OOFvOB

It.ElI.I3CM

I3.E4

GflMMfi-RBY ENERGY( 7, } --CREflTEK

i .e«.oi0-41

• .irE.M7.00

l.tK.M2.9E

IOJ1-0S

0.40

2. I0t«M

t.32

J.SSE.OS

1.11

THRU 0 .1 -

e.otcoot0-30

7.7IE«0«2.0D

3.UE.M0.14

• .0M.0BO.It

I.3DE<0t1.1S

1.IIE'Ot0.44

t.7tE<M1.31

J.JIE.Ot0.43

l.UE.Oi1.3*

I.77E»HC M


65.

64

65_

soZn

Abundance48 .60X

6C28INI

JAERI 1280 3. Graphs of Activation Dit» 135

10° JSZn TRRNSMUTRTION CROSS SECTIONS

- i c r 'L

ccCO

Iff1-4

•

icr3 10"1 10P 101 10* 103

NEUTRON ENERGY (EV!10* 10 s 10 s 107 ICP

NGNNHNTNflND

1((l(

JU-HR-3JU-IMI-3

19701970

1 KI3KI1 « N2N1 Z NNP1 * NP1

1(<t

SNL-76-34 197BJU-M-J 1870USE-50 197S

64soZn

NUCL1DE

3oZn

2SLU

scZn

2dCu

DECRY GRMMR-fHfiLFLIFE

9.13 H

250.0 0

9.76 M

38.40 M

12.80 H

6.11E.0647.00

B.11E.063.40

5.1 IE.05ltt.00

B.I It.05ltl.00

S.Olt.Dt91.00

?RY TRBLE

6.97E-06

24.00

1.12E-06

50.75

1.17E.06

0.3S

f.7OC<0S

(.40

1.3SE.0B

O.ED

4.0>E*0<

23.94

0.7SE.05

O.IE

*.ME>0>

DECRYYIELD

6.<«E'0E14.41

1.4IC*0t0.77

GflHMfi-RflY ENERGY('/.) — C»EOIE« THOU 0 . 1 -

B.OBE.OB

13.92

2.43E*0G

2.37

3.XE-0S2.1D

2.47E<0E

I.7S

;.60E<OS

1.27

3.60!«0B

0.42

4.50E-0I

0.24

1 .<K*0tO.IJ

1.1IE.MO.II

136 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission DaU JAERI1280

87

3oZn

66£u

65

KIP

"5 3 3 FT3oZn

Abundance27.9D7.

65

3oZn

64

3oZn

JAERI 1280 3. Gnpht of Activition Dtta 137

10P

-in-1

66L_

10"' _

a:CD

!0"3 _


:

(

'•

'•

'•

1 0 " ' I OP 101 10* 10s


10* 106 107 I0 9

KIGNfiNON3N

l1 N.0.T.I1 1973I1

1111

• — NZKI• NNP• NP

1 dm-75-54 H7E[ JU-RII-3 1970( U.D.T.l] 1973

11)

3o in

NUCLIDE

3oZn66

2=Cu

DECRYHflLFLIFE

92.00

250.0

5.30

GRMMfl-RRY TRBLE

Y

D

M

6.11E.05

3.40

5.I1E-05

o.oo

1.12E-06

50.75

1.D*E-Ot B.SSE«05

g.oo o.ii

DECBY

Y I E L D

GfltiMfl-RRY ENERGY

CREflTEIt THRU 0 . 1 -

138 Graphical Representation of Transmutation and Decay Chain Data, Transmutation JAFRI 1M0Cron Section and Delayed Gamma Ray Eminion Data JIE.IUI.COU

68

3oZn

ioZnAbundance4.107.

663oZn

65. 65

3oZn

JAERI1280 3. Gnphi of Activation Data 139

1 f r i

col

LJCO

l t r «


: J*

•

10"3 10"2 10-' 10° 10' 10* 103

NEUTRON ENERGY ( EV!

10* 10s 10s !0 7 109

• NG I• NP 1 JPERI-H-63S4 1916• ND I

' N3KI I• KI?KI (• W I U . D . T . I ! 1 9 7 3

67.3oZn DECRY GRMhH-RRY TRBLE

NUCLIOE

2ECU

3oZn

2sLu

HRLFLIFE

5-30 H

2S0.0 D

61.00 H

S.I1E-05O.OD

S.11E-06

3.40

5.1]E*0S

0.00

1.0<E-0B

B-00

1.1SE.06

50.15

1-B5E-0S

41.00

8.39E*0E

0.14

8.33E-OI

16.SJ

DECflV

Y I E L D

S.13E-D*

7.29

GflMMFI-RRY ENERGY

( X ) --C»EOTE» THHU 0 . 1 -

3.00E-05

0.14

3.t4E*DS

0.70

: .O>E*OS

0.11

140 Graphical Repietentation of Tianimutation and Decay Chain Data, TiaiumutationCron Section and Debyed Gamma Ray Emiuion Data

JAERI1289

6 %

369L3oZn

Abundance18-807.

673oZn

66

JAERI 1280 3. Graphs of Activation D m 141

10,-i a^n TRflNSMUTRTION CROSS SZCTIONS

S i (T

LUen

a:

10"3 10"2 10"' 10° 101 102 10'NEUTRON ENERGY (EV)

10* 10s 106 107 109

- N G . i• NGn 1• MR I N . D . T . l l 1913• ND I

' N3N I

I JU-Hlt-3 1910

3oZn

NUCLIDE

69m.

2 ^ 1

2dCu68

DECRY GRMMR-RRY TRBLEHALF

LIFE

52.00 M

13.80 H

2.55 H

61.00 H

30.00 S

6 . n E . 0 5

0.00

5.HE-05

O.OD

5.11E-05

0.00

5.11E-05

0.00

B.I IE.05

0.00

«.39E-0E

91.SO

I -«E-06

23.50

1.«5r-05

<1.00

6.J6E.0B

T.Wi

1.1JE.0E

15.19

«.33E.0<

I6-B3

8.46t40l

11 .B6

DECBY

Y I E L D

3-B5E.0S

t.lt

|.1K*O>

1.J»

1.0«E«D6

53.13

DBMMR-RfiY ENERGY

f'/. ) — CHEOIEII

I -B?E-O»

O.»>

5.ODE-OS

0.1«

1.1 IE-OS

1G.C2

1.1ZE>0«

O.'O

S.Kt-05

0-70

1.J6E.0S

1?.53

HRtl 0 .1 -

5.0JE-05

O.90

2.0IC-0I

0.1]

1.3<E<0f

1D.U

6.09C*OS

0.15

t.31E<0S8.36

1.0«E-OS

• •21

l.Kt.Ot

E.SO

142 Graphical Repietentatioii of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data

71JL

3oZn

t71

soZn

O

7 ]P3lU0

NP 3oZnAbundance0.62X

693oZn "SB":

69,Ga

JAERI1280 3. Gnphsof Actuation Data 143

10° T R f l N S M U T R T I G N C R 0 5 S S E C T I 0 N S

a:

Sio-1

LxJ

to

to

l O " 2

J :

•

•

10"3 10"2 10"1 10P 101 10 2 10 3

N E U T R O N ENERGY ( E V !

10* 10s 10s 107 I06

I V . 0 . 1 . 1 1 1973I JREKI-H-6354 I

DECRY GRMMfi-RRY TRBLENUCLIDE

3cZn

3o2n

3cZn

zdCu

HfiLFLIFE

2.40 M

4.10 H

S6.00 M

5.00 S

6.HE-06

0.00

6.HE.06

0.00

5.HE.OS

O.OD

S.11E.05

O.00

S.12E«DC

30.00

J.86E-05

92.00

6«5E«05

M.00

e.]0E<05

7.38

(.97E-06

62.?5

1 .«K>0>

OECBY

YJELO

3.BOE.05

3.63

J.JOE.06

56.70

OflHMfl-RftY ENERGY

(V.) --C'EOTEt IHOW 0.1-

1.22E«0E

6.1JE-06

2«.23

1.12E*0G

2.D6

6.86E.06

27.93

6-67E'O5

0.9S

1.4JE.0S

5.61

9.6SE-0E

0.73

9.65E-06

1.30

5.99E.05

o.cg

7.B3E.08

J.?6

7.21E'O5

0.62

1.21E.0S

2.89


8 7

91

Abundance51 -50-/

8839Y -"55".E lf t)U~"

88

JAERI 1280 3. Graphs of Activation Diti 1*5

10°90_ TRANSMUTATION CROSS SECTIONS

lO- 'L

co 1

COo

CJ

10-1LT3 10"2 10"'10P 101 102 103

NEUTRON ENERGY 1 EV 110*

• ND' NNfl• KIT• NRM

• NB n

• ND

I ENDF/B-4 1974

I 0NL3ZS 1976( H . D . T . l l 1913I

- N3KI• N 2 N .• N 2 N "• NNP n

• MNP• NP

RNL-15-3J 197S

JU-RR-3 1970U . D . T . I ] 1913

. 1 1 ' I 1

•

I•

:

:

10s 106 107 108

90_

NUCL1DE

87a

T-Rbsolr8 8 Y391

inZr89a

391

9 Q Y391

DECflY GRMMfl-RRY TflBLEHflLF

LIFE

2.83 H

•«.80E-»10Y

85 .00 D

108.1 D

78.<0 H

1.18 M

16.50 S

63.70 H

DECfiY GRMMfl-RflY ENERGY

YIELD r/.) -CHEOTE^ IHP» o. i -

5.11E«0S

0.00

S.llEÔS

0.00

S.]lE>05

0.00

S.11E*DS

14.00

S.!lE<05

J.97

5.)1E'OS

0.00

3.8BE-05

f?.00

3.t4E*0S

97-30

1 .B<t-00

«S.?4

9.09E«0S

99.01

G.8SE+0E

89.60

B.09E*05

99.14

O.9»fO5

tl .37

1.TIE.06

0.17

1.S1E-0S

G.E2

O.U

1.14E>0B

0.13

146 Giaphical Representation of Ttaiumutation and Decay Chain Data, TiantmutationCIOM Section and Delayed Gamma Ray Eminkin Data JAERI1280

SBTBUD"

Abundance11 -20X

90

Z

39I

8 '39

•-€&•

88

JAERI1280 3. Graph! of Activition D»t» 147

10' _

lcr1 _

C/3

Sio-2

1 0 " 3 _

1 O - "

TRRNSMUTPTION CROSS SECTIONS

;

;

;

' ' • • •

V.:

/ i

y1Q-3 10-2 iol itf io3

N E U T R O N E N E R G Y ( E V J10* lO5 I06 107 1CP

- KIG I ENDF/B-' ]97<• NR I• N3N (

• VIP ( M . O . T . I ] 1 9 7 3• W P " ( U . O . r . l l 1 9 7 3

91

4oZr DECRY GRMMR-RRY TRBLE

NUCL1DE

JoZr

Sir39lt

HflLF

LIFE

78

16

SB

50

40

50

60

30

H

S

D

M

5

s

• HE-OS

44.00

• HE.05

0.00

.11E«O5

0.00

•IIE'OS

O.OD

B.09E-DE

99.0)

».09E.DE

99.11

1.JOE-06

0.90

9.5»t-05

«4.90

1.71E'O5

0.77

DECftY

YIELD

I.74C06

0.13

ORHMfi-RfiY ENERGY

I'/.} —GREfiTER THBH O. I -

148 Graphical RepreMntation of Transmutation and Decay Chain Date, TransmutationCross Section and Delayed Gamma Ray Emission Data JAhRI 1260

88

939

NP

•3750TT

91

Zr

Abundonce17.10Z

39

39

JAERI1280 3. Gapht of Activation Data 149

10° _

crCD

JO"1 _

10"2L


1 1 1 1

L

S_1.

, , , . , , , . ( . , 1

I

i'•

•

•

10'3 10"2 10"' 10° 101 102 ! 0 3


10* 10s 10P 107 10P

' NG I EtlDF/B-4 1974' NKIR [• MR I M.D.T . l1 1913

• N3N (• N2N I' UP ( BNL32S 1816

loZrNUCLIDE

93 -

93i"

3eSr

3919 2 Y391

DECRY GRMMR-HflLFLJFE

1 -50E-OBY

13.60 Y

52.70 D

16.80 S

3.50 H

5.1IC0!Q-OG

E.11E.OE

0.00

=?RY TRBLE

S-OSI-05

9S.1«

S.35E-D5

I3.9D

K41E.06

4.19

DECRY

Y I E L O

E.G1E*OG

2.4!

GRMHfl-RfiY ENERGY17.) --CREOTEB IMflN O.J-

4.4SE.0B

2.34

«.44E.O5

I.E5

5.ISE.0S

0.63

«.»3!>tlS

0.49

) -BSE.OS

0.3t

1.I3E*OB

0.24

ISO Gnphical Reprewntation of Traiumutation and Decay Chain DaU, Tnuumutation IAFRI i ?finCrou Section and Delayed Gamma Ray Emiuion Data

9439

939

95

Z

-41•

94

,Y—micZr

Abundonce17 .40X

INI

923a

B- 9 2 vr —2".7IH""*39I92

qt 91

9039

90-7

JAERI1280 3. Graphi of Activation D*ta 151

(XCD

10"z _

toO

10"3L

io-4 _

ID"6

icr3

TRRNSMUTRTION CROSS SECTIONS1 • • ' '

;

I

V

1 1

\

j

•

icrl ICP IO1 IO2 io3

N E U T R O N E N E R G Y ( E V )

10* 10s 10P 107 ICP

• NG I EMDF/B-4 1974- NNR i' MR ( M . D . T . l l 1173• ND i' N3N I

• NNP ( II .D.T.1-1 1973' KIP I U . O . T . l l 1S73• N H E 3 1

DECRY GRMHR-RRY TRBLE

NUCL1DE

957

4llMb

90c

3a5r

I9V

391

Sly391

S2r4oZr

4 ^

39V

SSr

HflLFLIFE

65.50 D

90.00 H

38.00 0

28.80 Y

63.10 H

9.10 H

SO.30 M

53.80 D

10.10 H

1.50E+06Y

13.60 Y

20.30 PI

2.11 H

3.54 H

E.JIE'06

0.00

6.I1E-06

O.ODS.JIE-OS

0.00

t.iioot0.00

7.67E«0B

64.60

2.56E.06

2E.6S

7.HE.05

n.ti

<.HE«M

(l.lt

7.24E-0B

44. ?7

J-04E-OE

2-40

I.O/E-Oi

33.00

DECOY CflMMB-R

Y I E L D t X )

2.JSE-05

0.T4

T.Mt-Ot

23.01 7.70

BY ENERGY

—CKEflTER 1HOU 0 .1 -

••S3C*K

4.71 3 . H

*.i»«Ot

: • • •

t.IK'M1.74

I.7H.M1.13

6.IIE.06

0.00l.57E.0«

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1 .f{E*06

1.40

6.80€.O«

0.6]

1 .«IE-(»

0.94

I.4K-OI

0.24

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0.17

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l.HE.Ot

O.OO

t.nc«w0.00

»i«-mH . M

1.3K«K

M . M

1-14E-M

*.0i*.IK«0t

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(.f!C>W

4 . M

4.tlE»W

3.3i

I.OC.CK

1.41

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J.ME-OS

1.04

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D.(7

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o.n

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0.70

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0.30

|.»»€-O»

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1AERI1280

9 7 K V

92C

3 a.92

JAER11280

96_

3. Graphs of Activition Data

TRANSMUTATION CROSS SECTIONS

153

10° _

a:

.10"1 _

LLJ

to

o

1 0-3 |_

icr<

•

PL

r \i •

•

10"3 10"2 ID'1

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10° 101 10* 10'

NEUTRON ENERGY (EVI

10* 105 10P

• KI3KI I- N2N !• NP ( M.D.T.Il IS73- NHE3 (

NUCLIDE9 7 _

Vh

saSr

39V933EOr

391

391

«oZr

9 4 -3s5r

39T

39T

4^Zr

4 * ^

DECRYHALFLIFE

17.00

1.00

72.00

2.71

3.54

8.SO

10.10

10.90

65.50

90.00

35.00

0.7S

18.70

6.00

1.50E-"

13-60

GAMMfl-

H

M

M

H

H

M

H

M

D

H

D

S

M

S

06Y

Y

5.UE-0S

E

S

S

S

E

E

E

S

5

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B

I

0.00

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O.OO

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0.00

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0.00

11E.D6

O.OO

IIE'OS

0.00

IIE'OS

O.OD

11E-05

0.00

1IE-05

0.00

]]E'O5

O.OD

11E-06

0.00

1IE«DE

0.00IIE'M0.00

RRY TRBLE

7.43E->05

92.50

7.<3E«06

97.90

B.50E-D5

M.2D

1-S8E-D6

60.0D

i.lOE'OB

73.00

2.67E-06

E.ao«.6«E»06

19.00

7.67E-05

54.60

2-36E-05

25.65

7-55E-05

l-«3E-05

95.40

1-19E-0B

66.00

1 •«»•»

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5.07

1-02E*0B

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1.95

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44.27

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2.40

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l.HE-06

6.DS

1

1

4

I

1

3

2

7

S

DECPY

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2.ES

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0.16

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3.35

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24.74

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0.24

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4.11

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r/.)3.6SE»0S

2.26

J.52E.08

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21.42

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1

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1.20E<DC

D.IO

i.eiE.otl.EO

l.WE.Ot

0.S1

154 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCron Section and Delayed Gamma Ray Emission Data JAERI1280

4iNb

ci &

93m4lNb

94

Abundance100.00X

91ML4iNb

JAERI1280 3. Gnpiu of Activation Data 155

I01

10° I

CO

S10-5

10"6 _

10-1 _

io-8


! ' ' ' 'L ' i i 1 1

" ^ w ^ p J - u ^ - - - ^

!

1 f

t

1,

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" j

10"3 10"2 10"l ICP 101 10 2 10 3

NEUTRON ENERGY ( E V )10* 10s 106 107 ICP

• N G n

• NG .• NNR"- NNR• NNT• NT

ENDF/B-4 1974jnER]-M-E3S4 1916EUDF/B-4 1974

ENDF/B-4 1974

" NO- KI3KI• N2N• KIKIP• K J P• N2M"•MHE3

ENDF/B-4 1974

ENDF/B-4 1974U . O . T . I ] 1973

ft*NUCL'OE

9 1 Y

391

4iNb

39(

9 0 Y391

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LIFE

58 .50 D

6.29 M

2.00E*04Y

1E.80 S

63.70 H

10.62 D

I.S0E»06Y

13.60 Y

3.20E-«07Y

6.11E«06J

0.00

B.11E-0S

O.OO

t.l lE'K

0.00

B.llE'OS

O.OO

?RY TRBLE

•-71E-0E

0.40

t.71E*05

100.00

7.0SE.05

•a .oo

I.MEtOC

M.20

t.JK.Ot

l . t l

l.34E»05

OT-20

S.lK.Oi

1.6S

DECBY

Y1EL0

I.ISE«Ot

0.71

1 .WE-06

0.79

GBHMB-RBf ENERGY

{'/.) —CRERTE* THOU O . t -

156 Graphical Representation of Transmutation and Decay Chain Data, TransmutationCross Section and Delayed Gunma Ray Emission Data JAERI 1280

91.

Abundance14.80X

Z

3 9

83991

•«BU«i«t841

JAERI 1280 3. Gaphs of Activation Data

10° J H . TRRNSMUTRTION CROSS SECTIONS

157

1CT

• N G _• N G "

• N2Nn

• NB_• Nfl"• NP

N . D . T . l l 19*73N.D .T . I I (NG'2.01 1973N . 0 . T . I 1 1973N . O . T . U 1973N . 0 . T . 1 1 1973N . D . T . U 1973N . O . T . U 1913

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4310

NUCLJDE

* %93rn

43 lO

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8 9 a

8£4iNb

lh4iMb

4iNb894iNb

DECRY GRMMR-HBLFLIFE

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13.60 Y

6.9S H

15.49 M

64.00 S

62.00 0

78.43 H

16.06 S

4.18 M

3.20E+07Y

10.14 0

5.67 H

18.82 S

14.60 H

66.00 M

S.11E-05

to.co

5.11E>05

1«7.SO

S.11E.OE

70.79

E..HE.06

0.00

5.11E-05

0.00

5.11E-05

0.006.HE-06

GO .00

E.11E*O5

0.00

E.11E.OG

IOB.00

5.11E-05

20D.OO

RRY TRBLE

6.85E-05

88.68

1 .tiE.06

0.32

5.S3E.05

48.10].21E*0S

3.42

9.3IE-0S

99.20

g.34C>05

99.20

2.67E-0S

77.60

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82.71

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S9.SB

1.48E>0B

99.10

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24.25

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9.I3E.05

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S.15E.05

1.69

1.2!E-0E

B4.IB

DECRY

Y I E L D

2.63E-05

55.80

2.65E-00

0.12

!.Z1E*OB

18.67

1 .B5E.06

0-79

1 .S5E.0O

0.79

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1.3BE-06

0.7S

2.24E<0S

0.73

4 -4BE.06

6.07

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O.ES

9.5DE-05

0.1?

1.03E.0B

0.E3

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1-S3E.06

t.lE

9.4JE-06

6.S?

1.1BE.06

0.29

1.J7E«06

4.09

I.26E-0S

0.17

4.27E«04

2.H

7.33E*0B

0.17

1.4EE-05

I.SS

2.32E.0J

•2 .00

1.63E.06

3.CO

1.41E.0G

6t .« :

1.83E»06

3.39

2.I»E.O«

n . as3.09E.OB

3.IB

I.33E»OB

4.14

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2.77

l.SlE*Oi

2.39

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2.20

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2.00

I.S1E.01

1.73

2.96E*0B 1

?•« 1

1.27E<DE

1.30

9.21C0B

1.50

158 Giaphical Representation of Transmutation and Decay Chain Data, Transmutation IAFRT I ?snCross Section and Delayed Gamma Ray Emission Data M l u "

914oZr

94m4i|\!b

93.m,

4 11

;HAbundonce9.30/i

(NJl

42M0

4x2M0

JAERI1280 3. Grtphi of Activition Dtti 159

*i%

101 _ .

l t r 'L

1 0 " d _

JO"4


1

n

te,_.......H TH~T

•

/ i

^ ;

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10"3 10"2 10"110P 10" 102 103

NEUTRON ENERGY (EV)10* 10s 10s

• NP I N .D .T . l l 1973• NP I N .D .T . l l 1913' KI2N I N . D . T . n 1013

' KI2KI I U . D . T . m u : U ' 0 . 0 1 ) 197J I• HJG ( 110-NBT I N . 0 1 EHDF/B-4 1974 I' KIR I KFK-23B6 1077 I

101 ICP

DECflY GflMMR-RRY TRBLENUCLIDE

4 iNb

42JI093m

HSLF

LIFE

2.03E*:

6-26

3500

13.60

6.9S

4Y

M

Y

Y

H

DECRY

YIELD

GRMHfi-RfiY ENERGY

IX) —CftOTER THIMI O . I -

160 Graphical Representation of Transmutation and Decay Chain Data, TnnimutationCrass Section and Delayed Gamma Ray Emission Data

JAER11280

92-

Abundance %15.90'/.

JAERI1280 3. Gnphs of Activation DaU 161

102

101 _

Sio° _


10"l Q " 3 1 0 " 2 10" 1 10P 1Q1 1 0 2 1O3 10* 1 0 s 1 0 5 1 0 7

N E U T R O N E N E R G Y ( E V )• NP I N . D . T . I ] 1973 I• NP I N.D.T-1] 1913 1• N2N C KFK-2386 1977 I' NG I nO-NKT IH.G) EHDF/S-4 1974 1

• NR I KFK-Z386 1977• NNP,, ( N . O . T . l l 1973" NNP" ( N.0.T.J1 1973


NUCL1DE

AM)

3k\%

HRLF

LIFE

34 .97 D

86 .60 H

2.03E*D4Y

6.26 M

DECRY GRHHR-RRY ENERGY

Y I E L D t V.) - -Gf fEOTER THHH 0 . 1 -

162 Graphical Representation of Tianimutation and Decay Chain Data, TransmutationCron Section and Delayed Gamma Ray Emittion Data

Abundance16.70X


102 TRflNShUTflTION CROSS SECTIONS

10"10 ' 10* 103

NEUTRON ENERGY ( E V :104 10 s 106 107 I OP

• N P 1 N . O . T . l l 1 9 7 3• N N P . I N . O . T . l l 1 9 7 3• N N P " ( N . O . T . l l 1 9 7 3

• NP 1 N . O . T . l l 1973 1• N2KI I KFK-J3B6 1977 I' NG I HO-NRT IN.GI ENDF/B-4 1974 I


NUCLIOE

95mA llNU

HflLFLIFE

23.35 H

34.97 D

86.60 H

1.53E+06Y

13.60 Y

S.llE'050.00

7.78E«0S96.90

5.69E-0565.70

DECRY

Y I E L D

1.09E-06

49.40

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4.6OE'O5

18.19

8.S0E*05

20.73

l.ZOE«OB

?0.05

8.10E-05

9.93

7.J0E-05

7.30

4.51E-0S

6.33

164 Gnphical Representation of Transmutation and Decay Chain DaU, Transmutation IAPBI \isaCross Section and Delayed Gamma Ray Emission Data J * " "

Abundonce9.607.

94

JAERI1280 3. Gnphs of Activation Data J65

102 .?H TRRNSMUTRTION CROSS SECTIONS

10' _

1CTID" 3

10"' 1CP 101 102 103

NEUTRON ENERGY ( E V )10* 106 107 109

• N P I N . D . T . I 1 1 9 7 3• N P I N . D . T . I 1 1 9 7 3• NNP I (J.O-T.IJ 1973 • NB

I KFK-Z3B6 1977 II HO-NftT (M.DI ENOF/B-4 1974 I1 KFK-2386 IS77 I

DECRY GRHMR-RRY TRBLE

NUCLIDE

"Nb

HRLFLIFE

72 .10 M

60.00 S

23 .35 H

DECRYYIELD

OfiHMR-RfiY ENERGY( V. ) — GREr.TER THRM 0 . 1 -

5.J1E-050.00

7.7BE-0596.80

5.69E-0555.70

1 09E.06ie.4O

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2B.19

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20.73

1 .JOE'OB

20.05

0. lOt-05

9.93

7.20E.05

7.30

4,eiE*D5

6.33

166 Graphical Representation of Transmutation and Decay Chain Data, Tranimutation IAPBI I MOCrou Section and Delayed Gamma Ray Emiuion Data l * u u u ™

99

l * 4 3TC • • -? :

Abundance2 4 . 1 OX

42110


101

10"


10"2 10"1 1CP 101 102 103

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• NG ( ENDF/B-3 1970• N N P . ( N . D . T . l l 1973• NNP ( N . O . T . l l 1973

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t u .D .T .n( JU-RR-3I KFK-2386

19731970

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11)


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icZr

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72.10 M

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2.86 S

51.30 M

63.98 D

1 -S3E*06Y

31.97 D

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0.00

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0.00

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0.00

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89.00

7.38E.0E

5.60

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7.33E»05

12.60

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6.41

7.87E-0E

3.JO

7.23E<0E

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6.33

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168 Graphical Representation of Tiammutation and Decay Chain Data, Transmutation JAF.RI 1280Cton Section and Delayed Gamma Ray Emiuion Data

1 0 1M B - 1 0 1 T B - l c

42H0 ""ITTSTFT* s I C "1"4~:3W" 4

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NEUTRON ENERGY IEV)107 108

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14.61 M

14.30 M

66.02 H

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6.11E*06

0.00

6.11E.05

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40

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Graphical Representation of Transmutation and D ?cay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

109

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Abundance0.89'/

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10'

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NEUTRON ENERGY (EV1id4

I O 5 IO 6 io7 i OP

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4-flg107_

108—

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DECRY GRMMR-RRY TRBLEHRLFLIFE

453.0 0

39.20 C

6.49 H

44.30 S

2.42 M

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5.I1E.060.00

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JAERI1280 3. Gnphi of Activation Data 175

102 "fcd TRRNSMUTRTION CROSS SECTIONS

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253.0 D

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7.21

176 Graphical RepiesenUtion of Tiansmuution and Decay Chain DaU, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

108

45

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CM

10941

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101

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178 Graphical Representation of Transmutation and Deny Chun D»ti, TransmutationCross Section and Delayed Gamma Ray Emission Data

IAPRI nan

1 1 '4

113

In? I AbundanceI 4EC(J! 2 4 . 1 0 ^

109

109 - ' V

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JAERI1280 3. Gnpht of Activation Dtta 179

ai ",ti TRRNSMUTRTION CROSS SECTIONS

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NEUTRON ENERGY (EV)• N G , I ENDF/B-4 1974" NG" (• NB ( M.o-T . 11 1913

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13-60 Y

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39.20 S

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190 Graphical Repiesentation of Traiumutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data

JAERI1280

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113.

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1 13,

4

Abundance12.207.

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4


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10-' io° IO1 in2 io3

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X N2KI I EMOF/B-4 1974» NR I EHDF/B-4 1974* NP ( ENOF/B-4 1974

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NUCL1DE

DECRY GRMMfl-RRY TRBLEHPILF

LIFE

48.60 11

5.3T H

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3.16E-05

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6.73E-05

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0.72

3.33E.O5

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3.39E-05

o.;e9.e9E*0S

0.43

I.19E-0E

0.40

182 Graphical Representation of Transmutation and Decay Chain Data, Transmutation J AERI1280Cross Section and Debyed Gamma Ray Emission Data

11

4

115,

4

'S^~l

"2VaOTf - • 4"td

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Abundonce28.70/ i

%':

•~<?mi

11 I

JAERI128O 3. Graphs of Activation Data 183

]02 "fcj TRRNSMUTRTION CROSS SECTIONS

10"IO1 IO2 io3

NEUTRON ENERGY (EV!10* id5

IO6 107 10P

• nc i• NG I ENDF/B-4 1914• Nfl I M.D.T . I1 1913• N3M I

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( N . D . T . I 1 1973

DECRY DRMMR-RRY TRBLE

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39-50 n

125.0 D

2 .12 M

18.00 M

250 .0 D

2 .00 M

35 .00 Y

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212 Graphical Representation of Transmutation and Decay Chain Data, Transmutation IAFHI I 7»nCron Section and DeUyed Gamma Ray Emission Data K M

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214 Graphical Representation of Transmutation and Decay Chain Data, Transmutation IAFBI 19RI1Cross Section and Delayed Gamma Ray Emission Data

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220 Graphical Representation of Tnuumutation and Decay Chain Data, TransmutationCross Section and Delayed Gamma Ray Emission Data JAERI1280

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4. Concluding Remarks

Activation data for 116 stable nuclides of interest in terms of fusion reactor design aregraphically represented using the AMOEBA code. The graphical representation and the check-ing of the activation data proved to be very effective in correcting inappropriate data. Thecompilation of the graphs is a useful reference in the examination of activation problems infusion reactors.

As the result of the present work, the following areas appeared to require furtherimprovement in the future.(1) Activation reaction cross sections need considerable addition and re-evaluation.(2) Inelastic reactions resulting in metastable states should be considered.(3) More nuclides should be added as it becomes necessary.

Acknowledgements

The authors thank K. Minami, M. Kimijima and K. Tachikawa of Fujitsu Limited forthe preparation of a part of the activation data libraries. They thank H. Ihara of the JapanAtomic Energy Research Institute (JAERI) for the valuable discussions on the decay schemediagram. They are also grateful to K. Sako and Y. Obata of JAERI for their encouragements inperforming this work.

JAERI1280 247

References

1) HDA H., SEKI, Y. and IDE T.: J. Nucl. Sci. Technol, 14 [11], 836 (1977).2) ENGHOLM B.A.: GA-A16072, "Preliminary Radiation Criteria and Nuclear Analysis for ETF", (1960).3) SANTORO R.T., BARNES J.M., LILLIE R.A. and ALSMILLER R.G., JR.: ORNL/TM-7999, "Dose

Rates from the Induced Activity in the ETF Neutral Beam Injector", (1981).4) GOHAR Y., ABDOU M.A. and JUNG J.: "Radiation Shielding", Chapter 10, INTOR/NUC/81-10, The

U.S. Contribution to the International Tokamak Reactor Phase-I Workshop-Conceptual Design, INTOR/81-1(1981).

5) SEKI Y., IIDA H. and KAWASAKI H.: J. Nucl. Sci. Technol., 19 [1],11 (1982).6) IIDA H. and IGARASHI M.: JAERI-M8019, "THIDA-Code System for Calculation of the Exposure Dose

Rate Around a Fusion Device", (1978) [in Japanese].7) NAKAMURA T., MAEKAWA H., TANAKA S., SEKI Y., IKEDA Y., OYAMA Y. and IGUCHI T.:

"Integral Experiments on Lithium Oxide Spherical Assembly with Graphite Reflector and on DuctStreaming", Proc. 3rd IAEA Technical Committee Meeting and Workshop on Fusion Reactor Design andTechnology, Tokyo, Oct. 5-16, 1981, to be published by the International Atomic Energy Agency.

8) CINDA 7J- An Index to the Literature on Microscopic Neutron Data, International Atomic EnergyAgency, Vienna (1978).

9) SEELMANN-EGGEBERT W., PFENNING G. and MUNZEL H.: "Karltruher Nuklidkarte", 4. Auflage,Kerforschungszentrum, Karlsruhe (1974).

10) SEKI Y. and IIDA H.: JAERI-M8818, "Coupled 42-Group Neutron and 21-Group Gammi Ray CrossSection Sets for Fusion Reactor Calculations", (1980).

11) REYNOLDS J.T., LUBITZ C.R., ITKIN I and HARRIS D.R.: KAPL-3327, "Evaluated Cross Sections forthe Hafnium Isotopes", (1967).

12) LEPPAEMAEKI H. and KANTELE J.: JU-RR-3, "Table of Cross Sections of Some Reactions Induced by14-15 MeV Neutrons", Jyvaeskylae University, Finland (1970).

13) DRAKE M.K. (edited): BNL-S0274 (T-601, TID-4500), "Data Formats and Procedures for the ENDFNeutron Cross Section Library", (1970).

14) ALLEY W.E. and LESSLER R.M.: "Neutron Activation Cross Sections Measured and Semiempirical",Nuclear Data Tables 11,8-9(1973).

15) DRAKE M.K. (edited): BNL-50274 (T-601, TID-4500), "Data Formats and Procedures for the ENDFNeutron Cross Section Library", ENDF 102, Vol. 1 (1970) Rev. 1974.

16) GOEL B.: KFK-2233 "Graphical Representation of the German Nuclear Data Library KEDAK", Part INonfissile Materials, (1975).

17) DAVEY W.G., GOIN R.W. and ROSS J.R.: ANL-75-34, "An Analysis of (N, 2N) Cross Section Measure-ments for Nuclei up to Mass 238", (1975).

18) GROSS W.G. and ING H.: Nucl. Sci. Eng., 58 377 (197S).19) GARBER D.I. and KINSEY R.R.: BNL-325 "Neutron Cross Sections Volume II, Curves", 3rd Edition,

(1976).20) TSUKADA K.: JAERI-M63S4, "Nuclear Reactions and Subsequent Radioactive Decays Induced by 14

MeV Neutrons", (1976).

21) GOEL B.: KFK-2386, "Evaluation for the German Nuclear Data Library KEDAK-3: Part I NonfissileMaterials, (1977).

22) HASEGAWA A.: "PROF GROUCH-G-II", to be published.23) MACFARLANE R.E., BARRET R.J., MUIR D.W. and BOICOURT R.M.: LA-7S84-M, "The NJOY

Nuclear Data Processing System: User's Manual", (1978).24) LEDERER CM. and SHIRLEY V.S. (edited): "Table of Isotopes", Seventh Edition, John Wiley and

Sons, Inc., New York (1978).

24S Graphical Representation of Transmutation and Decay Chain Data, Transmutation • APRI 15R0Cross Section and Delayed Gamma R»y Emission Data J A t t u " o u

Appendix Activation Data Checking and Plotting Code,

AMOEBA

The number of stable nuclides stored in the CHAINLIB library is 116 at present. Thenumber of transmutation cross sections in the CROSSLIB library is about 800 and there areabout 300 gamma ray data in the GAMMALIB library. The consistencies of large amount ofdata should be guaranteed to obtain a reliable estimate of induced activation in fusion reactors.

The AMOEBA code has been developed to check the consistencies of data in theactivation data libraries and to display their contents in graphs for further examination. Itsfunction, program structure and input/output descriptions are introduced in this appendix.

A.1 Function

The functions of the AMOEBA code are as follows:Checking functions(1) It checks the consistency of the CHAINLIB library data.

i) The number of the data for transmutation and decay chain is checked.ii) The symbol of the decay type is checked.

iii) The consistencies of the changes in atomic number, metastable state indicator andmass number involved in transmutation reaction or decay are checked.

iv) The existence of the activation chain table for an unstable nuclide is checked accord-ing to Table 1.

(2) It checks the duplicity, nonexistence and redundancy of the cross section data in theCROSSLIB library.

(3) It checks the GAMMALIB library data.i) It lists gamma ray intensity greater than 1.0 for close examination. Annihilation

gamma ray intensities greater than 1.0 are not listed.ii) It prints out the symbol of unstable nuclides without decay gamma data.

Plotting functions(4) Transmutation and decay chain scheme is plotted using the data in the CHAINLIB library

for each of the stable nuclides.(5) Transmutation reaction cross sections are plotted in the multigroup (42-group) format.(6) Delayed gamma ray emission data are shown in tabular form.

The checking of the libraries (1) ~ (3) is conducted for all nuclides while the plotting(4) ~ (6) are conducted only for the nuclides specified by the input data.

A.2 Program Structure and Subroutines

The program structure and processing flow of the AMOEBA code are shown in Fig. A1.The functions of the subroutines of the AMOEBA code are described below:

1. FTMAIN Set variable common address and initialize2. LIBCHK Check library data consistency3. ACTSDF Control plotting routines4. DCHAIN Draw transmutation and decay chain scheme5. SPECTRA Draw multi-group transmutation cross sections.

JAERI1280 Appendix Activation DaU Checking and Plotting Code, AMOEBA 249

Program Structure

ILIBCHK |

Processing Flow

FTMAIN

ACTSDF

IDCHAIN | 1SPECTR | | GAMTB |

Input nuclidenames #5

ISCALER | INUMEXP

I GRID |

/SAMMAUB7'/ CROSSUB

/Activation f /uansmutotion/^ /6omma n(chain table ( (cms sections ( (emissionday t the nuclidesV Vqf the nuclides y \gf the nudk

ray fdata (

nuclides V_

Fig. A1 Progttm structure and processing flow of the AMOEBA code.

,™ Graphical Representation of Transmutation and Decay Chain Data, Transmutation^ * Cross Section and Delayed Gamma Ray Emission Data

6. SCALE R Calculate a factor for normalization7. GRID Draw grid lines and frame8. ZNORM Normalize cross section values to fit the scaling9. GAMTB Draw gamma ray emission data table

10. NUMEXP Change numbers to the exponential format11. TYPECV Check the symbols need for transmutation reactions and decay type12. ZBUN Separate the name of the nuclide into atomic number Z, metastable

indicator M and mass number A.13. ZPLOT Plot nuclide symbols14. CLEAR Clear the storage area15. LOCAT Check the unused locations16. PENSET Choose the pen for plotting17. ERRCHN Error message printout for CHAINLIB18. ERRCRS Error message printout for CROSSLIB19. ERRGAM Error message printout for GAMMALIB

A.3 Input Instruction and Output Dascription

Input format of the AMOEBA code

#Card 1 (216)

ICMAX ; the number of nuclides for plottingIEMAX ; the number of energy groups, usually 42. (The 42-group structure is built in.)

#Card2(6E12.0)ZAIC ; the names of the nuclides for plotting[ICMAX1

The logical numbers required for input/output files and their uses are:logical I ~ 3 work filelogical 8 activation data file J2504. CHAINLIB. DATA (CH82)logical 9 cross section file J2504. CROSSLIB. DATA (CR82)logical 10 gamma data file J2504. GAMMALIB. DATA (GAM81)logical 5 card input (#1 and #2 cards),logical 6 output file

* plotter output fileJob control cards required for the AMOEBA execution in FACOM M-200 machine are

shown in Fig. A2.

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