钍基熔盐堆(Thorium Molten Salt Reactor-Liquid Fuel,TMSR-LF1)回路管道最高运行温度达650℃,高温服役下的管道蠕变-疲劳损伤分析及评定至关重要。目前仅ASME-BPVC-III-5-HBB规范中有适用于高温核一级管道的蠕变-疲劳损伤暂行评定方法...钍基熔盐堆(Thorium Molten Salt Reactor-Liquid Fuel,TMSR-LF1)回路管道最高运行温度达650℃,高温服役下的管道蠕变-疲劳损伤分析及评定至关重要。目前仅ASME-BPVC-III-5-HBB规范中有适用于高温核一级管道的蠕变-疲劳损伤暂行评定方法,但该方法对于复杂管道系统使用起来过于繁琐。本文旨在使用管道分析软件PepS软件实现高温核一级复杂管系的分析与结构完整性评估。首先结合管道结构在多种载荷组合作用下的截面应力状态解析解,进行管道截面应力分析及应力线性化,并将结果与有限元数值解进行对比分析,两者的误差结果基本一致。随后,利用PepS软件对TMSR-LF1回路管道进行了力学分析和结构完整性评估,结其蠕变疲劳损伤结果位于包络线以内,满足蠕变疲劳极限的要求。该研究将管道分析软件与ASME评定规范进行了有效衔接,明确了评定方法,实现了高温核一级复杂管系的蠕变疲劳评估。展开更多
The thorium molten salt reactor–liquid fuel(TMSR-LF1) has inherent safety features. The accident occurrence possibility and their consequences are much lower for the TMSR-LF1 than that of traditional reactors.Based o...The thorium molten salt reactor–liquid fuel(TMSR-LF1) has inherent safety features. The accident occurrence possibility and their consequences are much lower for the TMSR-LF1 than that of traditional reactors.Based on accident analysis, the maximum credible accident and the radioactive source terms of the TMSR-LF1 were first estimated. Then, the total effective dose of the maximum credible accident was calculated. Based on calculations, the cover gas flow rate can significantly affect the radiation consequences of the maximum credible accident when it changes from 0 to 10 L/min. If no cover gas is flowing, a site-area emergency would be required within the range of 50–73 m from the reactor. In the case of cover gas flow, only an abnormal notification and an alert two emergency class would be required within the range of 50 m.展开更多
Tritium release is one of the most concerning topics in nuclear power plants. Here, the tritium production in a 2 MW liquid-fueled molten salt experimental reactor(TMSR-LF1) was calculated by ORIGEN-S with an updated ...Tritium release is one of the most concerning topics in nuclear power plants. Here, the tritium production in a 2 MW liquid-fueled molten salt experimental reactor(TMSR-LF1) was calculated by ORIGEN-S with an updated cross-section library generated by TRITON in SCALE 6.1.3 code system. The results show that the tritium production rate and normalized tritium production rate of TMSR-LF1 are 8.90x10^(11)Bq/day and4.45x10^(11)Bq/(MW day), respectively. The environmental impact of tritium was analyzed via PC-CREAM 08 with an assumed 36 % release rate of tritium referring to the molten salt reactor experiment. During normal operations, the maximum tritium concentration is 1.4 Bq/m^3 under normal condition, and the corresponding individual dose to the public is about 1 μSv/a; under extreme conditions, the maximum concentration and corresponding individual doses are 11.8 Bq/m^3 and 9 μSv/a, respectively.Ingestion is the main exposure pathway and accounts for62 % of the total dose. Of this, 35 % is from organically bound tritium.展开更多
文摘钍基熔盐堆(Thorium Molten Salt Reactor-Liquid Fuel,TMSR-LF1)回路管道最高运行温度达650℃,高温服役下的管道蠕变-疲劳损伤分析及评定至关重要。目前仅ASME-BPVC-III-5-HBB规范中有适用于高温核一级管道的蠕变-疲劳损伤暂行评定方法,但该方法对于复杂管道系统使用起来过于繁琐。本文旨在使用管道分析软件PepS软件实现高温核一级复杂管系的分析与结构完整性评估。首先结合管道结构在多种载荷组合作用下的截面应力状态解析解,进行管道截面应力分析及应力线性化,并将结果与有限元数值解进行对比分析,两者的误差结果基本一致。随后,利用PepS软件对TMSR-LF1回路管道进行了力学分析和结构完整性评估,结其蠕变疲劳损伤结果位于包络线以内,满足蠕变疲劳极限的要求。该研究将管道分析软件与ASME评定规范进行了有效衔接,明确了评定方法,实现了高温核一级复杂管系的蠕变疲劳评估。
文摘The thorium molten salt reactor–liquid fuel(TMSR-LF1) has inherent safety features. The accident occurrence possibility and their consequences are much lower for the TMSR-LF1 than that of traditional reactors.Based on accident analysis, the maximum credible accident and the radioactive source terms of the TMSR-LF1 were first estimated. Then, the total effective dose of the maximum credible accident was calculated. Based on calculations, the cover gas flow rate can significantly affect the radiation consequences of the maximum credible accident when it changes from 0 to 10 L/min. If no cover gas is flowing, a site-area emergency would be required within the range of 50–73 m from the reactor. In the case of cover gas flow, only an abnormal notification and an alert two emergency class would be required within the range of 50 m.
文摘Tritium release is one of the most concerning topics in nuclear power plants. Here, the tritium production in a 2 MW liquid-fueled molten salt experimental reactor(TMSR-LF1) was calculated by ORIGEN-S with an updated cross-section library generated by TRITON in SCALE 6.1.3 code system. The results show that the tritium production rate and normalized tritium production rate of TMSR-LF1 are 8.90x10^(11)Bq/day and4.45x10^(11)Bq/(MW day), respectively. The environmental impact of tritium was analyzed via PC-CREAM 08 with an assumed 36 % release rate of tritium referring to the molten salt reactor experiment. During normal operations, the maximum tritium concentration is 1.4 Bq/m^3 under normal condition, and the corresponding individual dose to the public is about 1 μSv/a; under extreme conditions, the maximum concentration and corresponding individual doses are 11.8 Bq/m^3 and 9 μSv/a, respectively.Ingestion is the main exposure pathway and accounts for62 % of the total dose. Of this, 35 % is from organically bound tritium.
