Research on Wastewater Source Term in High-Temperature Gas-Cooled Reactor and the Environmental Impact at Inland Sites

Yichun Zhang, Chuan Li, Haiyang Li, Jian-zhu Cao
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Abstract

High-temperature gas-cooled reactor (HTGR) is paid more attention in terms of inherent safety, high efficiency, and less liquid radioactive waste. The research on the source term of wastewater and the discharge methods of liquid effluent from HTGR can not only reduce the possible radiation risk to the environment and the public, but also promote the construction of inland nuclear power plants (NPPs), and improve the public acceptance of inland nuclear facilities. In this paper, calculation of activated corrosion products (ACPs) in the cooling water systems have been done in HTR-PM (High-Temperature Gas-Cooled Reactor Pebble-Bed Module) under normal operation conditions. Besides, the discharge methods of liquid effluent from inland NPPs without receiving water or with poor dilution conditions are studied. The calculation results indicate the cooling water of the heat removal system and shielded and component cooling water system needs to be changed once during the 40-year lifespan. The cooling water of the reactor support cooling system does not need to be changed. The annual effective dose resulting from liquid effluent through liquid-to-gas discharge using the data from a typical inland NPP site in China is less than direct discharge into the receiving water. The liquid-to-gas discharge is suitable for inland NPPs without receiving water or with poor dilution conditions.
高温气冷堆废水源期及内陆场址环境影响研究
高温气冷堆(HTGR)因其固有的安全性、高效性和较少的放射性液体废物而受到越来越多的关注。研究高温气冷堆废水源区及液体流出物的排放方式,不仅可以降低对环境和公众可能产生的辐射风险,还可以促进内陆核电站的建设,提高公众对内陆核设施的接受程度。本文对高温气冷堆球床模块在正常运行条件下冷却水系统的活性腐蚀产物(ACPs)进行了计算。此外,还研究了内陆核电站不进水或稀释条件差的液态废水的排放方法。计算结果表明,在40年的使用寿命内,除热系统冷却水和屏蔽及组件冷却水系统需要更换一次。反应堆支撑冷却系统冷却水不需要更换。利用中国一个典型内陆核电站场址的数据,通过液转气排放产生的液体废水的年有效剂量小于直接排放到接收水中的剂量。液转气排放适用于不取水或稀释条件较差的内陆核电站。
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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