Pellet cladding mechanical interaction as a potential failure mechanism during a control rod drop accident in a boiling water reactor
Creators
- 1. Idaho National Laboratory, Computational Mechanics and Materials, P.O.Box 1625, Idaho Falls, ID, 83415 (United States)
- 2. Oak Ridge National Laboratory, Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, One Bethel Valley Rd., Oak Ridge, TN, 37831-6172 (United States)
- 3. Constellation, Nuclear Fuels, 200 Exelon Way, Kennett Square, PA, 19348 (United States)
Description
Boiling water reactors (BWRs) represent approximately one-third of the operating fleet in the United States, contributing significantly towards the global effort in reducing carbon emissions. Even though most of the operating fleet has been in operation for quite some time, continued advancements in new nuclear fuel (such as accident tolerant fuel) or operating regimes (such as power up-rates and higher burnup operation) necessitates similar advancements in modeling and simulation capabilities. Bison, a component of the Virtual Environment for Reactor Applications (VERA), is a high-fidelity fuel performance code able to explore the fuel performance of a wide variety of fuel types in one-, two-, and three-dimensions. Until recently, the code had not been used for analyses of BWRs. Modeling capabilities have been added for Gd-bearing UO2 and pure zirconium liners. New models have been added based upon the U.S. Nuclear Regulatory Commission (NRC) guide-lines for hydrogen pickup in Zircaloy-2 claddings and pellet-clad mechanical interaction (PCMI) failure during a reactivity insertion accident (RIA), known as a rod drop accident (CRDA) in BWRs. Implementing and/or improving Bison modeling capabilities extended its analytical reach to areas beyond its original intended purpose. This paper demonstrates one of these capabilities as a proof of concept. Recently developed models enable Bison to provide an alternate approach for cladding integrity determination in CRDA evaluations, which currently use bounding conservative estimates. As part of this demonstration, NRC guidance on hydrogen-pickup and PCMI failure models were utilized in this research. Even though more research is needed in establishing right inputs and process in this area, this paper demonstrates Bison's ability to determine cladding integrity in a CRDA evaluation. This first of a kind demonstration is a proof of concept in this area, which could potentially be extended to a number of other areas where a more accurate cladding integrity determination would be needed. (authors)
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-787-3
- Imprint Title
- Proceedings of the international conference on physics of reactors - PHYSOR 2022
- Imprint Pagination
- 3701 p.
- Journal Page Range
- p. 2222-2230
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR 2022
- Dates
- 15-20 May 2022
- Place
- Pittsburg (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54002359
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; FUEL ELEMENT FAILURE; ROD DROP ACCIDENTS; ZIRCALOY 2
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-2; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; COMPUTER CODES; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FAILURES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NICKEL ADDITIONS; NICKEL ALLOYS; POWER REACTORS; REACTIVITY INSERTIONS; REACTIVITY-INITIATED ACCIDENTS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 17 refs.