50 s1 @ ' DOE-HTGR-87090 ORNL/TM-11346 EXPERIMENTAL TEST PLAN: COLLABORATIVE PROGm I USDOE/JAERI M FOR THE COATED PARTICLE F'UEL PERFORMANCE TEST ~~ AUTHORS/CONTRACTORS Oak Ridge National Laboratory M. J. Kania Japan Atomic Energy Research Institute K. Fukuda Oak Ridge National Laboratory Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, MC. for the UNITED STATES DEPARTMENT OF ENERGY December 1989-
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50 s1 @ ' DOE-HTGR-87090
ORNL/TM-11346
EXPERIMENTAL TEST PLAN: COLLABORATIVE PROGm
I
USDOE/JAERI M FOR THE
COATED PARTICLE F'UEL PERFORMANCE TEST ~~
AUTHORS/CONTRACTORS
Oak Ridge National Laboratory M. J. Kania
Japan Atomic Energy Research Institute K. Fukuda
Oak Ridge National Laboratory Oak Ridge, Tennessee 37831
operated by MARTIN MARIETTA ENERGY SYSTEMS, MC.
for the UNITED STATES DEPARTMENT OF ENERGY
December 1989-
This report has been reproduced directly from the best available copy.
Available to DOE and DOE contractors from the Office of Scientific and Techni- cal Information, P.O. Box 62, Oak Ridge, TN 37831; prices available from (615) 576-8401, FTS 626-8401.
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, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com- pleteness, or usefulness of any information, apparatus, product, or process dis- closed, 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 consti- tute 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.
DOE-HTGR-87090 ORNL/TM-11346 Distribution Category UC-522
Metals and Ceramics Division
EXPERIMENTAL TEST PLAN: USDOE/JAERI COLLABORATIVE PROGRAM FOR THE COATED PARTICLE FUEL PERFORMANCE TEST
-
M. J. Kania and K. Fukuda
Date Published - December 1989
Prepared for DOE Office Advanced Reactor Programs
AF 20 10 15 2
Prepared by the OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831-6285
operated by MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-840R21400 _ _ - - - _-
I
Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.
Schematic of the U.S. two-particle system for HTGR fuel . . Schematic of the J A E R I particle design. fuel compact. and graphite block element . . . . . . . . . . . . . . . . . Horizontal section through capsule HRB-21
Vertical section through capsule HRB-21 Horizontal section through capsule HRB-22
EXPERIMENTAL TEST PLAN: USDOE/JAERI COLLABORATIVE PROGRAM FOR THE COATED-PARTICLE FUEL PERFORMANCE TEST
M. J . Kania and K. Fukuda*
ABSTRACT
This document describes the coated-particle fuel performance test agreed to under Annex 2 of the arrangement between the ‘
U.S. Department of Energy and the Japan Atomic Energy Research Institute on cooperation in research and development regarding high-temperature gas-cooled reactors (HTGRs). The test will evaluate the behavior of reference fuel compacts containing coated-particle fuels fabricated according to the specifications for the U.S. Modular HTGR and the Japanese High-Temperature Engineering Test Reactor (HTTR) concepts. Two experimental capsules, HRB-21 and HRB-22, are being tested. Capsule HRB-21 contains only U.S. reference fuel, and HRB-22 contains only JAERI reference fuel. Both capsules will be irradiated in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Labora- tory (ORNL). volumetric fuel temperature of 975°C and will achieve a peak fissile burnup of 26% fissions per initial metal atom (FIMA) and a fast fluence of 54.5 x lo2’ neutrons/m2. Capsule HRB-22 will be operated at a mean centerline fuel temperature of 1250 to 1300°C and will achieve a peak fissile burnup of 5.5% FIMA and a fast fluence of 1.7 x lo2’ neutrons/m2. Performance of the fuels during irradiation will be closely monitored using on-line fission gas surveillance. capsules will undergo detailed examinations and core heatup simulation testing. Results from in-reactor monitoring and postirradiation testing will be analyzed to comparatively assess U.S. and Japanese coated-particle fuel performance.
Capsule HRB-21 will be operated at a mean
Following irradiation, both
I
1. SCOPE
Pursuant to Article 111-2 of the Implementing Arrangement between the
U . S . Department of Energy (USDOE) and the Japan Atomic Energy Research
Institute (JAERI) on cooperation in research and development in the area
of high-temperature gas-cooled reactors (HTGRs), the parties have agreed
*Department of Fuels and Materials Research, Japan*Atomic Energy Research Institute, Tokai Research Establishment, Tokai-Mura, Ibaraki-Ken 319-11, Japan.
1
2
to establish a collaborative program to conduct-a fuel performance test.
This program is currently evaluating the performance of reference fuel
compacts containing coated-particle fuels that have been fabricated
according to the specifications for the U.S. Modular HTGR (MHTGR) concept
and the Japanese High-Temperature Engineering Test Reactor (HTTR) concept.
Two irradiation capsules, designated HRB-21 and HRB-22, are used.
Capsule HRB-21 contains only USDOE reference fuel compacts, while capsule
HRB-22 contains only JAERI reference compacts. The USDOE-fuel was
fabricated by General Atomics, Inc., (GA) according to MHTGR fuel product
specifications, and the JAERI fuel was fabricated in Japan by Nuclear Fuel
Industries according to HTTR specifications. Quality assurance (QA)
characterization of both the USDOE and the JAERI fuels' was performed at
GA prior to start 0.f irradiation.
designed, fabricated, and assembled at the Oak Ridge National Laboratory
(ORNL). Reactor (HFIR) located at ORNL. Postirradiation examinations (PIES) will
be performed both at GA and ORNL, and the core heatup simulation tests
(CHSTs) will take place at ORNL. The analysis of test.results will be
The experimental capsules were
The irradiation is being performed in the High Flux Isotope
,
performed jointly by ORNL, GA, and JAERI, with the final documentation
being issued by ORNL and JAERI.
This experimental plan describes in detail the capsule design, fuel I t
compact designs and loadings, irradiation and surveillance requirements,
PIE and CHST matrices; documentation requirements, and the projected
schedule.
2 . OBJECTIVES ~. . . ~ . ~.~
The objectives of this collaborative program are to determine the
following for both the USDOE and JAERI reference HTGR fuel compacts:
1. the capacity of low-enriched uranium (LEU) coated-particle
fuels to meet their respective performance goals under normal
irradiation conditions, and
the capability of irradiated coated-particle fuels to meet
The QC results" performed-on a's'large numbcri-of cue1 compacts; from each I ".. - ,
fuel loading zone, are shown below.
consumed in making the 'heavy-metal contamination determinations using a hot
HC1 gaseous leach.process, . and from 15 to 20 were . . used for thi: defective Sic determinations bgsed -. -. I on a burn/leach pro1cedure. - - 1 ,The data ,are provided 1 -
in terms of the fractioniof heae metal removed by the destructive! QC
process to the total: heavy-metal content of all the samples te'sted! from
measurements-will be performed on each,-,fuel compact and graphite body and
at selected locations along the graphite sleeve. -These,will ,include
, I . (i -'-, . ' d
I t . . . , ' . ? ' . - - % ,.
, - 3 - - - ' . : r i . ; .
29
Table 10. Tentative postirradiation test matrix for JAERI annular fuel and USDOE cylindrical fuel compacts irradiated in
capsules HRB-22 and HRB-21, respectively
Compact a TRIGA Ceramography/ Decons 0.1 idat ion/ number ' microprobe IMGA~
JAERI annular compacts, HRB-22
1 2 3 4 5 6 7 8 9 10 11 12
X
X
X
X
X X X X
X X X X
X
X X
X
X
X
X
USDOE cylindrical
X X X X
X
X
X
X
compacts, HRB -21
X X X X
X
X
X
X
X X X X
a In capsule HRB-22, number refers to compact .location in graphite sleeve from the top of the capsule. In capsule HRB-21, number refers to the position of the graphite fuel body.
bCore heatup simulation testing. . CJAERI fuel. compacts must be deconsolidated prior to leaching d'Irradiated microsphere gamma analyzer.
step.
30
measuFements . -. . . ~% of - ~ the~>diameters.and.lengths . & . - of the compacts, fue,l bodies, and
sleeve, along.-with -,additional measurements to characterize fuel-hole
diameters in the fi-451. graphiteLbodies and wall ihickAess of the POCO AXF- 5Q--grapEite-sl-eeve; - - - For a -selected number of 3AERI- annular fuel -compacts
and USDOE.~cylindricaL,.fuelL ciompacts',- weight will 'also be:measured.
' I
1 , b . -
I~ . . ~ ,
. , . - - ~
7.2 TRIGA ACTIVATION-
Following the fuel and graphite component metrology, a number of J A E R I
and USDOE fuel compacts will be selected for TRIGA activation measurements.
The selected compacts will be shipped to GA for the activation and
analysis.
performed during the TRIGA irradiation.
J A E R I has requested that isothermal and isochronal heating be
(Specific compacts have not been
identified.)
7.3 LEACH
Because J A E R I fuef particles are overcoated-with a 200-pm-thick
layer, acid leaching of the annular fuel compacts will no,t provide useful
information. Therefore, the J A E R I compacts must first be deconsolidated,
and the remaining unbonded particles and graphitic material must then be
subjected to the acid leach.
7.4 CERAMOGRAPHY AND ELECTRON MICROPROBE ANALYSIS - .__.-.. . . ~ .
CerGographic examinations .will be ,performed on sections of the J A E R I . /
I .
annular and USDOE cylindrical' fuel' compacts ., . I, , ,Unbonded particles obtained by deconsolidation will also be used. .,me s i - ceramographic mounts will also
be available for electron microprobe analysis. , The,microprobe analysis
will be directed toward determining;fission product . \ distributions .~ .within
the fuel kernel and interaction with the coatings. Particular attention
will be given to the Pd-Sic chemical interaction.
7.5 DECONSOLIDATION AND IRRADIATED MICROSPHERE GAMMA ANALYSES
Deconsolidation procedures developed at ORNL have been used for the
relatively low-density reference design U . S . fuel compacts and not the
high-density reference J A E R I compacts. Thus, the electrolytic procedures
must be optimized for the dense J A E R I annular compacts. USDOE and J A E R I
31
compacts will first be subjected to a deconsolidation, and the recovered
unbonded particles will then be individually analyzed with the irradiated
microsphere gamma analyzer (IMGA). Failed-nonfailed decisions are based on
the relative inventory of a volatile fission product to the inventory of a
chemically stable fission product,. such as Cs:Ru.
7.6 CORE HEATUP SIMULATION TESTING
Four core heatup simulation tests'(CHST) have tentatively been chosen
for both the USDOE and J A E R I irradiated fuel compacts, including:
J A E R I compacts :
Test 1: 2000".C; ramp to temperature in 50 h;
Test 2: 1800°C; ramp to 1800°C in 3 h, hold at temperature for - 200 h; .
Test 3: 1600°C; ramp t o 1600°C in 3 h, hold at temperature for 997 h; and .
Test 4: 1600°C; ramp to 1600°C in 50 h, hold at temperature for 100 h, ramp down in 850 h.
USDOE compacts :
Test 1: 1400°C; ramp to 1400°C in 10 h, isothermal test at
Test 2: 1600°C; ramp to 1600°C in 10 h, isothermal test at
,,Test 3: 1600°C; ramp to 1600°C in 10 h, isothermal test at
Test 4: 1800°C; ramp to 1800°C in 10 h, isothermal test at
1400°C for 1000 h;
1600°C for 1000 h;
1600°C for 1000 h; and
1800°C for 500 h.
A l l of the CHSTs will be conducted in the Conduction Cooldown Test Facility (CCTF) now being constructed at ORNL.
provide simulation of the conditions of a high-temperature HTGR core
heat-up and provide for the on-line measurement of fuel failure and fission
product release.
J A E R I annular fuel compacts will be subjected to heating tests in the CCTF.
This facility will
A minimum of four USDOE graphLte fuei bodies and four
The CHSTs will emphasize temperatures ranging from 1400 to 2000°C.
The key fission product releases to be measured are Cs, Ag, Sr, I , Xe,
and Kr.
capability to undergo a short reactivation in a facility available in the
The irradiated fuel compacts from HRB-21 and HRB-22 will have the
Bulk,Shielding.Reactor:-(!BSR)~ at ORNL. . This facility will permit the'
.,generation- of sufficient-.quantities oT radioactive-..iodine. and- xenon,
i isotopes in- the:. fuel: particles such:' that the.ir:release can be- monitored
during the CHSTs.. r.During.these tests,, only the- total release for'each,
isotope will be measured;"no:'attempt to. identify chemical species will be
made. - .
' - . _ 8. .TENTATIVE SCHEDULE,,
- ' 1 - , . 1.
/u ' .' . . . . .~ . I
1 ~ _ _ -
A tentative schedule for testing capsules HRB-21 and HRB-22 has been . .
developed.
requirements and intejference from. other experiments in the HRLEL.
This schedule is sugject t o HFIR startup and shutdown
Central Research Library Document Reference Section LaboratoryRecords Department Laboratory Records, ORNL RC ORNL Patent Section M&C Records Office C, A. Baldwin W. P. Barthold (Consultant) E. E. Bloom J. A. Bucholz T. D. Burchell E. D. Clemmer J. C. Cleveland W. P. Eatherly (Consultant) L. C. Emerson E. C . Fox W. A. Gabbard U. Gat R. K. Genung H. A. Glovier
D. W. Heatherly J. R. Hightower F. J. Homan 'D . T. Ingersoll H. Jones M. J. Kania P. R. Kasten (Consultant) T. S. Kress J. C. Mailen B. F. Myers F. R. Mynatt N. H. Packan P. L. Rittenhouse J. P. Sanders 0. M. Stansfield J. 0. Stiegler K. R. Thoms D. B. Trauger . A. W. Trivelpiece
EXTERNAL DISTRIBUTION
48. GENERAL ATOMICS, P.O. Box 85608, San Diego, CA 92138-5608
A. J. Neylan
49-55. JAPAN ATOMIC ENERGY RESEARCH INSTITUTE, Tokai-Mura, Ibaraki-Ken 319-11, Japan
K. Fukuda (5) T. Kondo K. Shiba
56. MODULAR HTGR PLANT DESIGN CONTROL OFFICE, P.O. Box 85608, San Diego, CA 92138-5608
R. R. Mills
57-59. DOE, DIVISION OF HTGRs, NE-451, Washington, DC 20545