SP-100 fuel pin performance: Results from irradiation testing

Conference · Wed Sep 01 04:00:00 EDT 1993

OSTI ID:10107574

Makenas, B J; Paxton, D M ^[1]; Vaidyanathan, S ^[2]; Hoth, C W ^[3]

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1. Westinghouse Hanford Co., Richland, WA (United States)
2. Martin Marietta, San Jose, CA (United States)
3. Los Alamos National Lab., NM (United States)

A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 10107574
• Report Number(s): WHC-SA--2091; CONF-940101--24; ON: DE94003466
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300
220600
BURNUP
CLADDING
EBR-2 REACTOR
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
IRRADIATION
NESDPS Office of Nuclear Energy Space and Defense Power Systems
PERFORMANCE
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
RHENIUM
ROD BUNDLES
SAFETY ANALYSIS
TESTING
URANIUM NITRIDES