Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise

Jie Mao, Qiliang Mei, Shengqin Gao, Dawei Sun, Yaru Fu, Jiaxin Liu
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Abstract

The fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter for analyzing the radiological consequences of Reactor Control Rod Ejection Accident (REA). Instead of a set of constant release fractions specified in RG 1.183 (2000), RG 1.183 (2023) has been revised the fuel rod gap release fraction to Steady-State Fission Products Release Fraction (SFGR) that are originally residing in the fuel rod gap and Transient Fission Gas Release Fraction (TFGR) that are related to burnup and Radial Average Fuel Enthalpy Rise (△H).This paper specifically analyzes the relationship between the fission products release fraction and △H under different burnup, and a set of relatively conservative calculation dose results are obtained based on the empirical data of a specific power plant. In addition, a sensitivity analysis of the effect of △H on the dose consequences is carried out, and the analysis results show that the dose consequences increases linearly with △H when exceeding the critical conditions capable of causing TFGR.
基于径向平均焓升峰值的反应堆控制棒抛射事故辐射后果分析研究
反应堆控制棒抛射事故发生后,存在于燃料棒空隙体(静压室和球团-包壳间隙)内的裂变产物可被释放,而裂变产物释放分数是分析反应堆控制棒抛射事故辐射后果的关键参数。与RG 1.183(2000)中规定的一组恒定释放分数不同,RG 1.183(2023)将燃料棒间隙释放分数修改为稳态裂变产物释放分数(SFGR),该分数最初位于燃料棒间隙和瞬态裂变气体释放分数(TFGR),该分数与燃燃量和径向平均燃料焓上升(△H)有关。本文具体分析了不同燃耗下裂变产物释放分数与△H的关系,并根据某电厂的经验数据得出了一组相对保守的计算剂量结果。此外,还对△H对剂量后果的影响进行了敏感性分析,分析结果表明,当超过能够引起TFGR的临界条件时,剂量后果随△H线性增加。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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