【摘要】 本文通过对西屋标准电厂技术规格书中一回路冷却剂放射性比活度限值的研究,揭示了限值制定的背景及含义,有助于对技术规格书中相关规定的深入理解和后续的执行。通过AP1000电厂与西屋标准技术规格书的比较可知,AP1000电厂技术规格书用剂量等效¹³³Xe比活度限值替代了西屋标准技术规格书中的总放射性比活度限值,剂量等效¹³¹I比活度和¹³³Xe比活度限值均基于设计基准0.25%燃料包壳破损率计算得到,屏蔽设计、三废处理系统设计和事故后果分析等所采用的源项是一致的。最后,结合国内标准要求给出了可以对技术规格书中碘尖峰时比活度限值进行调整以及剂量等效¹³¹I和¹³³Xe比活度限值可以根据0.25%燃料破损率计算数据进行调整的建议。更多还原

【Abstract】 The background and meaning of the limits formulation were revealed based on the study of the specific activity limits of primary coolant in Westinghouse standard specifications. This is helpful for the in-depth understanding and follow-up implementation of the relevant operation provisions. Through the comparison between AP1000 power plant specifications and Westinghouse standard specifications, it is found that the total specific radioactivity limit in AP1000 power plant specifications is replaced by the dose equivalent of ¹³³Xe specific activity limit in AP1000 power plant specifications. The dose equivalent of ¹³¹I and ¹³³Xe specific activity limit are calculated based on the design basis of 0.25% fuel cladding defect. The source terms used in shielding design, waste treatment system design and accident radioactive consequence analysis are consistent. Finally, combined with the requirements of domestic regulations and standards, some suggestions were given on adjusting the iodine spike specific activity limits and dose equivalent of ¹³¹I and ¹³³Xe specific activity limit according to the source terms of 0.25% fuel cladding defect.更多还原