Fuel fragmentation data review and separate effects testing
- 1. Electric Power Research Institute, Charlotte, NC (United States)
- 2. Studsvik Nuclear AB, Nykoping (Sweden)
- 3. Westinghouse Electric Company, LLC, Columbia, SC (United States)
- 4. ENUSA Industrias Avanzadas, S.A., Madrid (Spain)
Description
A simple alternative test has been developed to study the fuel fragmentation process at loss of coolant accident (LOCA) temperatures. The new test heats a short section of fuel, approximately two pellets worth of material, in a tube furnace open to air. An axial slit is cut in the test sample cladding to reduce radial restraint and to simulate ballooned condition. The tube furnace allows the fuel fragmentation process be observed during the experiment. The test was developed as a simple alternative so large number of tests could be conducted quickly and efficiently to identify key variables that influence fuel fragmentation and to zeroing on the fuel fragmentation burn-up threshold. Several tests were conducted, using fuel materials from fuel rods that were used in earlier integral tests to benchmark and validate the test technique. High burn-up fuel materials known to be above the fragmentation threshold was used to evaluate the fragmentation process as a function of temperature. Even with an axial slit and both ends open, no significant fuel detachment/release was detected until above 750°C. Additional tests were conducted with fuel materials at burn-ups closer to the fuel fragmentation burn-up threshold. Results from these tests indicate a minor power history effect on the fuel fragmentation burn-up threshold. An evaluation of available literature and data generated from this work suggest a fuel fragmentation burn-up threshold between 70 and 75 GWd/MTU. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting (WRFPM 2014)
- Imprint Pagination
- 784 p.
- Journal Page Range
- 7 p.
Conference
- Title
- 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting
- Acronym
- WRFPM 2014
- Dates
- 14-17 Sep 2014
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47079936
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CLADDING; COMPARATIVE EVALUATIONS; FRAGMENTATION; FUEL CANS; FUEL ELEMENT FAILURE; FUEL RODS; HEATING LOAD; LOSS OF COOLANT; PERFORMANCE TESTING; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K
- Descriptors DEC
- ACCIDENTS; DEPOSITION; EVALUATION; FAILURES; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SURFACE COATING; TEMPERATURE RANGE; TESTING
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: fullpaper100117.pdf; 15 refs., 12 figs., 3 tabs.