核安全2024，Vol.23Issue(6)：29-35,7.
压水堆核电厂乏燃料水池侧墙外剂量率影响因素的敏感性分析
Sensibility Analysis on Dose Rate Behind Side Walls of the Spent Fuel Pool in a PWR Nuclear Power Plant
杨煦 1蔡北国 2朱雷 2杨腊腊 1陈秋炀1
作者信息
- 1. 苏州热工研究院有限公司,苏州 215004
- 2. 福建宁德核电有限公司,宁德 352000
- 折叠
摘要
Abstract
At present,the spent fuel pool of CPR1000 pressurized water reactor(PWR)nuclear power plant,where 4.45%enriched fuel assemblies with short cooling time are stored near the side wall,may have the problem that the dose rate outside the side wall of the spent fuel pool exceeds the dose rate limit.In order to provide effective guidance for the radiation protection of the power plant and to improve the usage of the spent fuel pool,it is necessary to carry out a sensitivity analysis of the factors affecting the dose rate outside the side wall of the spent fuel pool.Three factors are calculated and analyzed by using the point kernel integration program QAD-CGGP,to evaluate the impact of the spent fuel assemblies'cooling time,the distance between the dose point and the radioactive source,and the thickness of the water sheet between the first row of assemblies and the side wall.The source term of the spent fuel assembly with 4.45%enrichment of a typical CPR1000 unit,the structure of the spent pool and the shielding characteristics of various materials are used in the calculation.Calculation results show that emptying the first four rows of assemblies closest to the side wall of the spent pool,or storing the spent fuel assemblies with longer cooling time(much longer than the current cooling time of 4 days)near the side wall can make the dose rate outside the side wall of the spent fuel pool satisfy the dose rate requirements.In order to ensure that the dose rate outside the side wall of the spent fuel pool does not exceed the limit,the results of this calculation can provide guidance for nuclear power plants to select the optimal spent fuel assemblies storage plan.关键词
乏燃料水池/剂量率/QAD-CGGP程序Key words
spent fuel pool/dose rate/QAD-CGGP program分类
能源科技引用本文复制引用
杨煦,蔡北国,朱雷,杨腊腊,陈秋炀..压水堆核电厂乏燃料水池侧墙外剂量率影响因素的敏感性分析[J].核安全,2024,23(6):29-35,7.
