压水堆LOCA放射性源项计算模型及应用研究

陈海英; 王韶伟; 田欣鹭; 吴彩霞; 熊文彬; 张春明

doi:10.7538/yzk.2020.youxian.0027

压水堆LOCA放射性源项计算模型及应用研究

生态环境部核与辐射安全中心,北京102401

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- 刊出日期: 2020-12-19

Research of Radioactive Source Term Calculation Model and Application in LOCA for PWR

Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing 102401, China

摘要

摘要: 根据压水堆冷却剂丧失事故（LOCA）后核素从堆芯迁移、释放至安全壳及环境过程中的产生和消减机理，建立了完整的LOCA放射性源项计算模型，并对模型计算结果进行对比分析，最终将模型应用于第3代压水堆LOCA源项计算分析中。结果表明：本文模型与TACTⅢ程序计算结果的相对偏差在±0.05%以内，与TITAN5程序的碘计算结果的相对偏差在±0.5%以内，本文模型计算准确。对于压水堆各种核电机型，安全壳内核素的去除机制及去除速率不同，导致释放到环境中的I和Cs核素活度变化曲线也不同，¹³¹I、¹³⁴Cs、¹³⁶Cs、¹³⁷Cs在事故后30 d内释放到环境中的累积活度逐渐增大。建立的模型基于完整的核素衰变链，考虑了母核衰变对子核源项的贡献及喷淋或自然去除等作用对元素碘的有效去除过程，通用性强。
- 计算模型 ,
- 第3代压水堆 ,
- 源项 ,
- 冷却剂丧失事故
Abstract: According to the mechanism of the generation and reduction of the nuclide in the process of migration and release from the core to the containment and the environment after the pressurized water reactor (PWR) loss of coolant accident (LOCA), the calculation model of radioactive source term for LOCA was established. The comparative analysis of model calculation results was carried out. Finally, the model was applied to the source term analysis for the third generation PWR LOCA. The results show that the relative deviation between the calculation results of the model and TACTⅢ code is within ±0.05%, and the relative deviation between the iodine calculation results of the model and TITAN5 code is within ±0.5%, so the model calculation is accurate. For various nuclear motor types of PWRs, the removal mechanism and removal rate of nuclide in the containment are different, resulting in different I and Cs radioactivity release curves. The cumulative radioactivity of ¹³¹I, ¹³⁴Cs, ¹³⁶Cs and ¹³⁷Cs released into the environment within 30 d gradually increases. The established model is highly versatile, which is based on the complete nuclide decay chain, considering the contribution of the precursor nuclides decay to the daughter nuclides, and the effective removal process of elemental iodine by spraying or natural removal.
- calculation model ,
- the third generation PWR ,
- source term ,
- loss of coolant accident

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文章访问数: 408
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压水堆LOCA放射性源项计算模型及应用研究

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Research of Radioactive Source Term Calculation Model and Application in LOCA for PWR

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