ML20205Q219

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Speech Entitled, Final Results of Qualification Testing of Triga Fuel in Oak Ridge Research Reactor Including Post- Irradiation Exam, Presented at 851014-16 Meeting in Petten,The Netherlands
ML20205Q219
Person / Time
Site: General Atomics
Issue date: 10/14/1985
From: Chesworth R, West G
GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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NUDOCS 8605280212
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{{#Wiki_filter:. Referanca '(g) GA Itr 67/9000 dated 5/20/86 FINAL RESULTS OF QUALIFICATION TESTING OF TRIGA FUEL IN THE OAK RIDGE RESEARCH REACTOR INCLUDING POST-IRRADIATION EIAMINATION BY t Robert H. Chesworth and Gordon B. West GA Technologies Inc. [ i Presented at the International Meeting on i Reduced Enrichment for Research and Test Reactors (RERTR) Petten (N.H.), The Netherlands 14-16 October,1985 l i 8605280212 860520 PDR ADOCK 05000163 P PDR

T~ o-i 1 i i d FINAL RESULTS OF QUALIFICATION TESTING OF TRIGA FUEL IN THE OAK RIDGE RESEARCH REACTOR INCLUDING POST-IRRADIATION EXAMINATION [ Robert H. Chesworth and Gordon B. West GA Technologies Inc. f P. O. Box 85608, San Diego, California 92138, U.S.A. i 1 As part of the qualification testing of TRIGA (uranium siroonium-hydride, rodded) low enriched uranium fuel, a 16-rod experimental cluster (Figure 1) was irradiated in the Oak Ridge Research Reactor (ORR) (Figure 2) between December 1979 and l August 1984. A total of 19 fuel rods, with three different fuel compositions have been tested - Er-U-ZrH containing 20, 30 and 45 4-weight percent uranium. Individual rod powers have been in the range of 25 to 53 kw and the test cluster operated in-core for 901 full power days. Some of the fuel test parameters are shown in Figure 3 In May 1982, after 575 full power days, the rods containing 20 and 30 weight percent uranium were removed, having attained a l burnup in the range of 50 percent of the contained uranium-235 This was higher than the init2al target burnup values of 35 and j 40 percent, respectively. Destructive examination of one rod l each of the 20, 30 and 45 weight percent fuel rods showed normal performance with no anomalies. Figure 4 shows the three rods destructively examined in the summer of 1983 They were the highest burnup 20 and 30 veight percent rods and one of the high l, burnup 45 weight percent rods. Irradiation of the 45 weight percent rods was continued to the target burnup value of 50% and extended into the burnup range of 55 to 65 percent of the contained uranium-235, up to a test cluster exposure of 901 full pcwer days. At this point, one of f j the fuel rods exhibited a clad failure due to steam buildup during a return to reactor power. Extensive analysis and post-1rradiation examination led to the conclusion that the failure originated in a cladding defect which became manifest af ter four l i 1 ,+------,~v-, ,--r------- ,,,n--.---

I GENERAL LAYOUT OF 16-ROD FUEL CLUSTER mui GA Tectmaaoges mum FUEL CLUSTER DIMENSION 8.100 CM (3.189 IN.) = = = 1 UDING D EARANCE 7.983 CM (3.135 IN.) (SAME AS CENTER TO CENTER = = CLUSTER SPACING) 8.805 CM (2.879 IN.) = = o l O O, <O, O I l < l l l l 2 l HROUD l l l l l } l l l = l l (2.879 N ) (2.98 N )i(3.035 N ) t 0.228-IN. O O Ol O l WALL l I I I I i l l j a l O O, ll l 1.833 CM (0.843 IN.) u FUEL PIN I i ll II r U l 3 L______q____J i o.151-IN. WALL O.953 CM (0.375 IN.) G-453(3) 10-7-85 EL-2686

i l LOCATION OF TRIGA LEU FUEL TEST CLUSTER IN ORR -caTechnoso,e mum l ^ WEST l 89.045 l 8 REGION NUMBERS 44 CONTROL ROOS i 75.395 -2 i 72.855 /- 3 1 2 3 4 5 84.750 41 I 3 8 7 Ijl. 9 l10! 11 l 3 58.885 ^^~ g m 3 12 34 13 14 15 18 17 l 0 48.570 O I E U 3 43 35 18 li! 20 l...21} 22 3g 42 R g w I 40.475 T 3 37 23 24 38 25 39 28 T I H 32.380 4 H ~ Z 27 28 @9j 30 31 32 33 24.285 4 N 3 40 NTRIGA LEU 18.190 14.285 -2 43 TEST BUNOLE 8 44 45 44 'j 2 4 2 iiiii 3 3 i 3 i,di g CM g 3 3 3 3 3 i 'X INTERVALS [ G G U M M 3 5 " E d E E G

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j e h TRIGA LEU FUEL ORR IN-PILE TEST l l 20 WT-% U 30 WT-% U 45 WT-% U l CONTAINEO U-235 PER 22 IN. FUEL R00 (GM) 19 30 55 I VOL-% U (19.7% ENRICHEO) 7 11 20 MAX CALC R00 POWER GENERATION (KW) INITIAL CONFIGURATION 36 35 u FULL CLUSTER CONFIGURATION 41 43 48 45 WT-% ONLY CONFIGURATION 55 TIME AT POWER (FPD) INITIAL CONFIG (DEC 79-NOV 80) 0 278 278 I FULL CLUSTER CONFIG (MAY 81-MAY 82) 295 295 295 45 WT-% ONLY CONFIG (JULY 82-NOV 83) O O 328 TARGET BURNUP OF U-235 (%) 35 40 50 FINAL BURNUP RANGE (%) 45-57 47-57 60-66 l G-453(6) l 10-7-85 i

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D 6 years and about 5 x 1021 nyt. Non-destructive examination of a large sampling (over 100)of similar cladding - Incoloy-800 - has led to the conclusion that this was a unique defect and not a generic characteristic of this type or batch of cladding material. The in-pile testing of the experimental cluster was reinitiated in July 1984 but was terminated shortly thereaf ter due to a cladding break caused by mechanical rubbing of the cluster spacers which resulted from removal of the thermocouple support member. The test was terminated at this point since all of the test rods had met or exceeded target burnups without difficulty. The burnup history of the 45 weight percent rods is shown in Figure 5 A comprehensive post-irradiation examination (PIE) campaign has been established for the 45 wt-5 fuel rods as the final step in the qualification of TRIGA low-enriched uranium (LEU) fuel. The PIE includes: Diametral and bow measurements of all of the 45 wt-5 rods Measurement of pressure inside intact rod 1089 or 1090 Identification and quantitative analysis of gas in free space inside of rod 1089 or 1090 Identification and quantitative analysis of gas contaired in fuel matrix of rod 1083 or 1090 Gamma scan of rod 1086 to determine peak-to-average burnup I Measurement of pressure and gas analysis of gasses in plenus of rod 1086 Performaace of metallography on rod 1086 Performance of burnup analysis on section from highest burnup region of rod 1086 l Performance of physical testing of selected cladding segments of rod 1086 Tests completed to date include only the gamma scan of rod 1086, and some of the metallography on samples cut from rod 1086. Rod 1086 is the rod with highest burnup. The gamma scan will l help determine the peak-to-average power in the rod and was also used to help determine the best locations for metallography and burnup samples. The gamma scan is shown in Figure 5A. The metallography on rod 1086 indicates no major differences from the metallography which was done on the 45 weight percent !y d -_m, .-----_.w ..,---_c w- -. - s_,,

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h BURNUP VERSUS FULL POWER DAYS 45 WT-% TRIGA LEU FUEL IN ORR i M 1HS 'TC = THEllAA0 COUPLE ELEGAENT l / i "FPD = FULL POWER DAYS I - 1888 l 4.00 80 I I88I 38 3 N l 1989 l 4.31 l \\ 1H2 TC* l 4.02 70 l \\1888 24 1 I A001993 FAILE0 1H3 3.74 AT 901 FP0" N 1H1 TC a. 3.45 80 -53% U-235 80 29.0 6 m T E a l m E 3.18 -N l $I E 2.07 - d 50 l 1994 23.0 g c s 1000 ~ E E 2.59 T 1989 l b 2.30 - ! 40 i ~ 1s's 1987 1 4 1890 2 II ~ 1000 R001000 14,3 *E l 1.72 30 l REIA0VE0 FOR l ANALYSIS AT 721 FPD I" 1992 TC~ i 1.15 20 l ~ 47% U-235 OU 9.2 l f 0.00 IN FillAL 8.57 10 III-CORE 48 l l l EXPOSullE l 1901 FPD) e i i i i i e 200 400 000 000 1000 1200 1400 FULL POWER DAYS 10RR) ) l NOTE: NORIAALIZE0 TO ORNL FISSION PRODUCT ANALYSIS ON B0051802,1000.1893. AND 1890 G-559(1) 10-7-85 l i L

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9 l fuel in 1983 (rod 1088) and in 1984 on rod 1093 The clad i failure occurred on rod 1093 The burnup values for the three rods examined, 1088, 1093 and 1086 are 47, 53 and 66 percent, respectively. 4 Typical sets 11ography pictures of rod 1088 are shown in Figures 6 through 9 They can be compared with typical I metallography pictures for rod 1093, shown in Figures 10 through 12. Pictures for rod 1086 were not available at GA in time to ~ include in the paper. l Figures 13 and 14 show a fuel-clad interface for rod 1093 There is no evidence of fuel-clad interaction. Meta 11ographic i pictures of the clad break surface for rod 1093 are shown in Figures 15 and 16. They show the characteristics of a typical ductile failure, with no evidence of embrittlement, corrosive attack or intergranular failure. i A picture from the scanning electron microscope (SEM) is shown in Figure 17 It also shows normal ductility. No shear faces were detected. I It is expected that the post-irradiation examinations and their documentation will be completed in the first half of 1986. l The LW uranium-sirconium hydride fuel has completed all essential development testing successfully. It is offered commercially in both 20 wt-$ and 45 wt-5 uranium concentration for existing TRIGA reactors and as a conversion fuel for plate-type reactors. Several reactor facilities have already begun conversion to LE uranium-siroonium hydride fuel. It is in use in a mixed plate-and-rod fuel configuration in the 1 W reactor at the I National Tsing Hua University in Taipei, Taiwan. A complete core l of 20 wt-5 4-rod shrouded cluster fuel has been fabricated and i shipped for conversion and upgrading of the PRR-1 reactor in the i Philippines. The converted reactor will operate at 3 MW with l forced cooling and have pulains capability. Startup is scheduled for early 1986. Also, a complete core of 20 wt-5 LE fuel has been fabricated for the 3 W forced-flow TRIGA Hark II reactor system with pulsing capability in Bangladesh. It is scheduled to l be completed in 1985 U-ZrH LW fuel has also been delivered to existing TRIGA reactor facilities in Malaysia, Thailand and Yugoslavia for their use as new fuel is needei to meet burnup requirements. ? l l l

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