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Cover Sheet for a Hanford Historical Document Released for Public Availability Released 1995 Prepared for the U.S. Department of Energy under Contract DE-ACOG-76RLO 1830 Pacific Northwest laboratory Operated for the U.S, Department of Energy by Battelle Memorial Institute
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Cover Sheet for a Hanford Historical Document Released for … · Cover Sheet for a Hanford Historical Document Released for Public Availability Released 1995 Prepared for the U.S.

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  • Cover Sheet for a Hanford Historical Document Released for Public Availability

    Released 1995

    Prepared for the U.S. Department of Energy under Contract DE-ACOG-76RLO 1830

    Pacific Northwest laboratory Operated for the U.S, Department of Energy by Battelle Memorial Institute

  • DISCLAIMER

    This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, make any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

  • DISCLAIMER

    Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

  • - -

    G E N E R A L E L E C T R I C HANPORD ATOMIC PRODUCTS OPERATION - RICHLAND, WASHINGTON

    DATA AS

    D O T H E R OFFlClAL CLASSIFIED INFORMATION

    TH1 S MATERIAL CONTAINS I NFOR MAT1 ON AFFECT1 NG T H E NATIONAL DEFENSE O F THE UNITED STATES WITHIN THE: MEANlNG OF THE ESPIONAGE LAWS, TITLE 18, U. S. C., SECS. 793 AND 794, THE TRANS- MISSION OR REVELATION OF WHICH I N ANY MANNER TO AN UNAUTHORIZED PERSON 1s PROHlBlTED BY

    F I L E DES I GNAT1 ON

    DOCUMENT NO.

    m-31905

    DATE

    May 20, 19% COPY NO. AND SERIES

    Critical. Mass Calculations f o r the Recuplex Izstal la t ion

    AUTHOR . . R. P. R a f t e r g

    P

    t t

  • C O M P A N Y I

    . . . . HANFORD A T O M I C PRODUCTS O P E R A T I O N

    c: 1. Fw Utm?gh >u.* GM Maler 2. R3 Beeton 12. WJ Ozeroff 3. VR C o o p e r 13. RP R d t e r y - D D L w n i n g 4. DE Davenport 7-494 14. WH R e a s 6. PF Gas t 7. OH Greager 8. OF Hill 9. E F K u r t z 3.0. WH Mobley

    5. JE F a u l h e r ~ m c r i i o t b ~ I I 3.5. AE -5th 16. GW Stuart 1-7. WK WDods

    21. 300 Files 22. Y e l l o w C o p y

    18-20. mrs.

    T h i s document consists of T h i s docwent c lass i f ied by B. R. Leonard

    11 pages. copy NO. / I I - of 22 copies. -

    CRITICAL MASS CALCULATIONS FOR TBE RECUPLEX INSTAIlLATIOR

    bY

    R. P. RaStery

    43 A P R I M E C O N T R A C T O R F O R T H E U.S. A T O M I C E N E R G Y C O M M I S S I O N

  • - 2- m-31905

    A B S T R A C T

    The methods of an aml.ysis of the c r i t i c& safety of process tanks

    i n the Recuplex instal la t ion ewe discussed and resu l t s of the

    analysis are tabnlated i n this report.

    f o r a thermal chain reaction

    f o r 400 MWD/T Pu f o r each tank i n the instal la t ion which normally

    contains, o r c o d & contain, plutonium. All estimates are based on

    experimental c r i t i c a l mass data from the P - l l project and from

    O a k Ridge crit ical . mass experiments.

    A minimum c r i t i c a l condition

    is estimated f o r 0-200 MWD/T Pu and

  • HW- 3 19G5

    h extensive exaBnation of t h e prcceas vessels in the Recupiex insfallation and t h e m a neutron ref lectors i n tke vfcizt ty of these vessels has been made. Since m m t y of these vessesP v e x Pculzii to 3e not aQways c r i t i ca l ly sgfe from them& cha2.n reactions, it i s ecessazy to establksh l i m i t s on the m a x i m u m aaouzt of plutonium which can safely be coa%&ned fn an;y one tank at any tiae. Subsequent t o the s 3. Ozeroff" of the chain reacting Units in the Recqlex p r o c e s z ? , a complete set of" pz5n-f~ of the installation was ob- tained and an exmination of each t u azd 2 t s swrounr?ings, as indicated on these primts, vas made with regar6 t o c r f % i c d safe53. examfnation, estfmates 400 MWD/T plutonium exposures of the rniz&mm c r i t i c a l condition f o r each vessel fn the ins ta l la t ion which acmaEy contatzs or9 tbough operational emoss, could contain plutonium in solution o r as a preeiipita-be.

    y made 37 W.

    A s a result of t M s have been ms2e %o%b on tfie basis of 0-200 MWD/T and

    11. KETSODS OF maysrs The ins ta l la t ion f s contained in t h e e large luc i te hoods i n the 234-3 Building, the slag and crucible hood, the solution receptfon and blending hood, and the solvent extraction hood. Each hood i s roughly 4.5' x 269 x 16' high. t t o n t o the actual process o r plutonlm--iearing tanks, each hood contains a supporting framework, process piping and associated valving and f i t t ings, process pmps, and auxiliary tanks. Each of these serves t o some degree as a thennal neutron ref lector for the product-bearing tgsks.

    In addi-

    Xn the following estimates, therma3. neutron ref lect ion from the supporting framework, process pumps, luc i te hood panels, the concrete floor, auxiliary tanks, pipes and f i t t i ngs , process t a d w a l l s , and operating personnel near product-bearing tanks' has been approximated by an equivalent reflector thick- ness f o r each hmlr. In addition, interactton between nemby product-bearing tanzks was taken in to account. upon the minrfmum c r i t i c a l conditions f o r each individual tank. pipes within one foot of each tank were assumed t o cross-sectional tank area by an axnoun$ equal t o the sum of the cross-sectional areas of the f l u i d i n all. pipes w i t h i z this distance.

    These two factors have a very significant e f fec t Product-bearing

    increase the effective

    The fo1lowing approximations were ma6e t o accomk f o r thermal neutron reflec- t ion from near3y objects:

    1) For ref lectors of ma21 cross-sectfond mea, such as small pipes and members of the supportfw framework,

    Equivalent refl. tlhic-kmess = Y w - R ,

    where R i s the &stance betwee2 the cen%erlines of the tank and reflec- t o r m d C.S,A. is t l e ez-oss-sectfond. area. of the reflector.

  • -le-

    current density out current density i n fl = albedo [refP. coef'f". of' actual r e f l ec to r =

    pa )= albedo of an i&ixxi%ely tMck r e f l ec to r surrounaing the process tank. The remaining quantit ies are shown i n the following diagram:

    ,(is plotted versus re f lec tor thickness i n Figure 1, taken from HW-25374. (2) This relationship between ref lector thickness and extrapolation length is based upon an extrapolation length of 6.1 cm in water.

    Estimates of the in%era?%fon between product-bearing vessels were made on the bas is cf experimental. data on the interaction between r ightcircular cyl2nders of several diameters containfng water solu%loss of 0-235 as reported i n K-406. The following empfrfcal equation WBS found 57 trial and error. experimental da ta quite we91 an3 is a good approximation within the given l imits.

    (3 1 It f i t s the

  • I I

    . *"

    w h e r e

    a = inside diameter of tank in inches

    _ c - A a - fTactfonal iacrease f n effect ive diameter of one tank due to the e f f ec t of the second. a

    d = edge - to-edge tank separation faa fnches = albedo for the combhed waSP thicknesses of t he interacting tanks

    o( and f l are indicated %n the fo l lowbg diagram:

    I

    _.--_ -

    Interact ion between product-bearing vessels of less than eight-inch inside diameter i n the Rccuplex in s t a l l a t ion was conside-red t o be that between two eight-inch cylinders. Eight inches i s the smallest diameter to which the experbente l data can be extrapolated. diameter vessels The in te rac t ion between large product-bearing vessels used process negligible. A discussion of this eqdation can be found i n HW- 29396. t'l Figure 2 i s a plot of the fnteract ioa between t w o para l le l eight- fncb r igh t circular cylfnders eQht feet fza lengbh versus the centerline-to- ce25erPfne separation of the vessleu f o r various r e f l ec to r thicknesses of stain- Zess s t e e l bekween the interacting cyltnlders. for the preceding equation i d ) I s 3 . 3 inches f o r eight-inch cylinders.

    The interact ion between smaller i s lower and therefore the above assumption is conservative.

    i n the Recuplex

    The lower l i m i t of separation

  • f -7-

  • i: - d- Ed-3 1905

    where

    V = volume of Pu solu%lo~ in l i ters

    r239 = cross sectlon f~ b v m , taken t o be ll5O

    W = Pu-240 fke l fraction, %&en as 0.0295 f o r 400 MWD/T and 0 ?OF 0-200 Mw3/T

    ~ p O i S O E 1 = nacroscop~c cross section, taker as 0.0220 cm-1

    These equations were derived on t e b s4 of' expeflaental data obtained from ?-I2 c r i t i c a l mass experbents. d, &,I8 1

    The pmduct-beariag ta&s haye bees d:vLaeed physfed inside tmk diameters, about sevea inches i s sZde diameter are reported e r l t i c d . concentration. t ed t o be s&e as l a g as the p2~i--lordm comeatration i n the tank the specffied Iiait. chosen fn repoPtfng mf&m critical concen%ra+,fons f o r these smaller tanks. T h i s w a s dloxie fn d e w of the so3aewha-t Q W t e d p

    prediction fomuLa f o r c r f t f ca l mass is based, predfctea by the ecpation exceeded ZgO gram per l i t e r f o r several tanks, but in view of %&e mcep',aicty of validity i z z ?&is range, the l i m i t s are reported as 150 grams per l i ter . L M t s for the Parp;er'.taz&s of about f i f teen inches inside fiameter and greater are r e p o ~ e d P a grams of plutodum, o r m i n i m u m c ~ L t f c a P mass, a =ore signifPfcm-b a d reali3SIc f " igze thm sa estfaated c r i t i ca l concextra- tioE. h the basis of' concez&Pa%iox, the ma5mm safe amount of plutonium fn these larger tanks v07d.3 be qxi%e high if 822. of the pl~~tozxirn in the tanks always reza2zed 5 3 so>snr;iez..

    i n to two groups oc. the basis of Mnimi c r i t i c a l conditions for mall tanks of

    i n grams per l i ter , o r minimum

    5s less than AB^ volume of solution i n one of these tanks i s estima-

    h mper cowentratiosa Pftnft of 150 grms per l i t e r was

    e of concentrations of plu- tordm s01ut;ions used fn the P-99 expenoisaents bY upon which the semiempirical.

    The allowable concentrations

    The &aimla81 c,-f$fc& miss of pfutonim i n these larger tanks i s

    "%&en, hcwever, %be pcss2biEty of a plutonium

  • - 9-

    precipi ta te exists, much higher than normal concentration of plutonium Could be present i n one section of such a tank and critical condftions m2gM be approached. Therefore, such calculations 8se based on the minfmum c r i t i ca l mass i n the tank rather than the m i n i m u m c r i t i c a l concentration, and result from the assumption of a homogeneous l a e of precipitate, water tamped on top and bottom, being formed i n the tank. T?T The following are estimates of the minimum c r i t i c a l conditions f o r product- bearing vessels i n t h e Recuplex in s t a l l a t ion based of approximation. The first table l ists the s m a l l diameter vessels and the second l i s t s those of comparatively large diameter.

    on the preceediu methods

    TABLE I

    Tank Estimated M i n i m u m Cr i t ica l Concentration f o r Number 0-200 MWD/T Pu 400 MWD/T Pu

    k/l) ( 8/11 31-31 G-16 G-17 G-28 G-42 G-46 G-47 G-48 G-50 G- 51 G- 54 E-1 ms H-1 COL E-1 BDS H-2 TDS H-2 COL H-2 HDS E-3 TDS H-3 COL H-3 BDS H- 9 H- 10 H-11 J- 1 J- 2 5-3 5-4 5-5 5-6 J-? J- 17 5-25 5-30 5-31

    Safe* Safe Safe Safe 90

    Safe 110 100

    85 135 Safe 100 SsSe 70

    100 Safe - 70 100

    -Safe 70 105 100 95 150 140 130 Safe Safe Safe 150 80

    Safe Safe Safe

    Safe* Safe Safe SaSe 135 Safe 150 150 120 150 Saf'e 150 Safe ' 95 150 Safe - 95 150 Safe 95 150 3-50 145 Safe 150 150 Safe Safe Safe Safe 110 S d e Safe S d e

    *Safe from thermal chain reaction for MWD/T Pu l is ted

  • D - l D-2 D-3 D-4 D-5 a- 6 D-Y D- 8 D- 9 D- 10 D-3.3. D- 12

    D- 26 D- 27 D- 28 G- 9 G- 10 G-15 a-36 a-44 e- 52 e-j8 K- 1 IC- 2 K- 9 L- 2 L-3 L- 8

    D- 23

    Tank Dbmeter

    28 28 14 14 29 31 31 30 30 16 16 16 22 2c 18 28 32 34 I 34 34 18 34 30 26 26 17 42 42 42

    1300 13m 670 650

    a3 00 agoo agso 1473 I430 675- 675 7@0 950 550 750

    k3@0 1 6 ~ ~ 1800 1800 a800 750 1800 1450 1200 2200

    2600

    2600

    650

    2600

    1450 1450 7 ~ 1 ~ 9 7501

    1400 1700 1700 1600 1600 775/P 775 775 1050 950 850 1450 1750 1950 1950 1950 850

    1950 1600 1300 1300 730

    2800 2800 2800

    Tiaese estimates as"e not v a l i d f o r exposures lower than those upon which they ape base&e For Xgher exposures they are somewhat con- servative. Thus, the es%bat,es in the first column are considered s d e f o r any W/T PU, wuse those i n the second are considered s d e for 400 MWD,~! pt1, or greater.

  • -11- Hw-31905

    REIPEREXCES x

    1.

    2,

    3 .

    4.

    5-

    6 .

    Ozerof'f', W, J., Chain Re&ct%ng %fn8%s i n the Reeuplex Process, HW-27491, Mwch 25, 1953.

    L m n i n g , D.D., C r f t f c d Mass Study of 231 Process Tanks. August 19, 3.932.

    HW-25374,

    F a d h e r , J. E., Davenport, D.E, , an6 I)sa.epaA,1, G.E., T e c U c a l Activit ies Report fop September, 1953, Pbysfcs U d t , Applied Research, Technical Section, Engineerfng Department, HW-29596, October 12, 1953.

    IIivesi, F. E., E r k m a , J. O . , and L a m i n g , I). D., HW-24514, Cri t ica l Mass Stud ies of Plutonfum Solutions, May 19, 1952.

    Lanning, D. D., lled t o Purex and Recuplex Design, Hw-27575, April 1, 1953.

    i Technical Section EPTGINEZRII'?G DEPARTMENT I

    Physics Unit