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压水堆核电厂氚排放源项的计算及验证 被引量:1

Calculation and Verification of Tritium Release for PWR Nuclear Power Plants
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摘要 氚是核电厂放射性流出物中重要的核素,氚源项也是核电厂辐射环境影响评价中最重要的关注点之一。本文基于压水堆核电厂中氚的产生机理建立氚源项的计算模型,并结合我国某在役核电机组2003—2018年运行经验反馈数据,对理论计算模型的结果进行对比分析。研究结果表明,本文建立的氚的计算方法所得到的模拟值与实际运行情况相符,本文氚排放计算采用的计算模型和假设是合理的。 Tritium is an important nuclide in the radioactive release of nuclear power plants.Tritium release is also one of the most important concerns in the radiation environmental impact assessment for nuclear power plants.Based on the generation mechanism of tritium for PWR nuclear power plants,the calculation model of tritium release is established.Combined with the operational feedback data from a nuclear power plant during normal operation in China in 2003-2018,the result of the theoretical calculation model are compared and analyzed.The research result shows that the simulation values obtained by the calculation method of tritium are consistent with the actual operation.The calculation model and assumption used in the calculation of tritium release are reasonable.
作者 杨昭林 王亮 周永海 周克波 吴华雄 柳顺雷 王昆鹏 叶远虑 YANG Zhaolin;WANG Liang;ZHOU Yonghai;ZHOU Kebo;WU Huaxiong;LIU Shunlei;WANG Kunpeng;YE Yuanlv(College of Environmental Sciences and Engineering,Peking University,Beijing,100871,China;The Nuclear and Radiation Safety Center MEE,Beijing,100082,China;State Environmental Protection Key Laboratoryof Nuclear and Radiation Safety Regulatory Simulation and Validation,Beijing,China;China Nuclear Power Design Co.,Ltd.,Shenzhen of Guangdong Prov.518057,China;Daya Bay Nuclear Power Operation Management Co.,Ltd,Shenzhen of Guangdong Prov.518124,China;China National Nuclear Corporation,Nuclear Power Operations Management Co.,Ltd,Haiyan of Zhejiang Prov.314300,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2020年第3期359-366,共8页 Nuclear Science and Engineering
基金 国家科技重大专项课题“大型先进压水堆及高温气冷堆核电站”课题(项目号:2013ZX06002001,2019ZX05006001)。
关键词 压水堆 核电厂 气液态放射性流出物 PWR Nuclear Power Plant Gaseous and Liquid Radioactive Release Tritium
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