FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new USNRC and current Swiss failure limits

被引:6
|
作者
Khvostov, G. [1 ]
Gorzel, A. [2 ]
机构
[1] Paul Scherrer Inst PSI, Forschungsstr 111, CH-5232 Villigen, Switzerland
[2] Swiss Nucl Safety Inspectorate ENSI, Ind Str 19, CH-5201 Brugg, Switzerland
关键词
RIA; Cladding failure; PCMI; Cladding embrittlement; Balloon burst; FGR; H-uptake; BURST FGR;
D O I
10.1016/j.net.2021.06.001
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Outcomes of the FALCON code analysis-related part of the STARS-ENSI Service Project on Evaluation of the new U.S.NRC RIA Fuel Safety Criteria and Application to the Swiss Reactors are presented. Substantial conservatism of the updated safety limits for high-temperature and PCMI cladding failure, as proposed in the NRC Regulatory Guide RG 1.236, is confirmed. Applicability of the updated failure limits to fuel safety analysis in the Swiss PWRs, as applied to standard fuel designs using UO2 fuel pellets and SRA Zry-4 as cladding materials is discussed. Conducting of new integral RIA tests with irradiated samples using doped-and gadolinia fuel pellets to support appropriate fuel safety criteria for RIA events is recommended. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
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页码:3741 / 3758
页数:18
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