Published 2022 | Version v1
Book

Pellet cladding mechanical interaction as a potential failure mechanism during a control rod drop accident in a boiling water reactor

  • 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)
Part of:
Proceedings of the international conference on physics of reactors - Physor 2022

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)

Optional Information

Notes
17 refs.