Welcome to the PSAM 16 Conference paper and speaker overview page.
Lead Author: Yong-Joon Choi Co-author(s): Chris Gosdin (cgosdin@fpolisolutions.com)
Gabrielle Palamone (gabrielle.palamone@fpolisolutions.com)
Cesare Frepoli (frepolc@fpolisolutions.com)
Jason Hou (jason.hou@ncsu.edu)
Safety Analysis of Accident Tolerance Fuel (ATF) with Increased Enrichment and Extended Burnup: Simulation Tools Review
One of the main obstacles for deploying near-term accident-tolerant fuels (ATFs) with higher burnup is related to successfully passing regulatory-required fuel safety assessments. A phenomenon called fuel fragmentation, relocation, and dispersal (FFRD) that is observed during postulated accident events may cause fuel damage exceeding the postulated safety limits. There have been multiple research efforts dedicated to investigation of the FFRD phenomenon and its consequences. However, most of them have focused on conventional fuel (e.g., non-ATF). The recent study by the U.S. Nuclear Regulatory Commission [1] addresses that fuel fragmentation can be observed starting from 55GWd/MTU burnup (average burnup of US nuclear power plant is 45GWd/MTU) for standard UO2 fuel during a design basis loss of coolant accident (LOCA). Generally, ATFs have advantage of better mechanical strength under high-temperature accident conditions over the traditional fuel (i.e., zircalloy cladding). The increased fuel enrichment and associated increased burnup would allow extension of refueling cycle from 18 to 24 months, which is a significant economic benefit for operating nuclear reactors. However, safety analyses of ATF with HBU are still incomplete especially in terms of FFRD, a necessary step for fuel to be licensed . The recently-initiated project under the Light Water Reactor Sustainability Program focuses on the investigation of the FFRD effects on the ATF with higher enrichment and burnup during a LOCA. The research scope includes the development of optimized reactor core configuration with ATF specific to a 24-month fuel cycle, fuel analysis with respect to the FFRD phenomenon, source term evaluation, and consequence analysis. The analyses within the scope of the project require multiple simulation models and an investigation of available computer codes was conducted to determine code applicability and capability to meet project goals. This paper summarizes the overall research plan as well as presents the results of the review of select simulation tools in the area of core design, system and accident analysis, and fuel performance.
[1] U.S. NRC, Interpretation of Research on Fuel Fragmentation, Relocation, and Dispersal at High Burnup, RIL 2021-13, 2021
Paper YO298 Preview
Author and Presentation Info
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Lead Author Name: Yong-Joon Choi (yong-joon.choi@inl.gov)
Bio: Since 2012, Dr. Choi is a program manager and senior research scientist at Idaho National Laboratory. In his capacity, he leads various programs under DOE's Light Water Reactor Sustainability program. He is also a member of RELAP5-3D nuclear thermal-hydraulics code development team. Prior to INL, he worked at the OECD Nuclear Energy Agency for seven years as program manger for developing advanced nuclear fuel cycles and related strategy and policy. Dr. Choi received his Ph.D. and grand master degree on thermal system energy from the University of Marne-La-Vallee, France, M.S. and B.S in nuclear engineering in Kyunghee University, Korea.
Country: United States of America Company: Idaho National Laboratory Job Title: Program Manager / Senior Researcher