压水堆核电厂氚排放量的系统设计分析  

Process Design Analysis on Tritium Discharge of Pressurized Water Reactor Nuclear Power Plant

作　　者：王艺霖 范雯雯 孙煜伟 高瑞发 WANG Yilin;FAN Wenwen;GAO Ruifa(China Nuclear Power Engineering Co.,Ltd,Beijing 100840,China)

机构地区：[1]中国核电工程有限公司,北京100840

出　　处：《核科学与工程》2022年第2期335-341,共7页Nuclear Science and Engineering

摘　　要：压水堆核电厂尤其是内陆核电厂的氚排放一直备受关注。目前关于压水堆产氚的计算分析通常以一回路冷却剂系统作为氚活度衡算边界,系统设计对氚排放量的影响少有讨论。本文将氚活度衡算边界从一回路扩展到反应堆冷却剂净化和复用系统,考察了一回路氚比活度控制值、反应堆冷却剂净化复用系统水装量和不复用排放水量等三个系统设计参数之间的关系和它们对压水堆氚排放量的影响。经分析发现,通过提高一回路氚比活度控制值和增加净化复用系统水装量,可显著降低氚排放量。基于现有的核电厂设计,若将一回路氚比活度控制值从15 000 MBq·t^(-1)提高到44 000 MBq·t^(-1),氚排放量设计值可以降低3%~13%,若进一步增加复用系统水装量到10 000 t,氚排放量设计值可降低46%。The discharge of tritium of pressurized water reactor especially those sited in inland territory has long been concerned. Works on calculation and analysis of tritium generation usually take the primary coolant system as the boundary of tritium activity balance. The impact of process design on tritium discharge has not been discussed. By expanding the boundary of tritium activity balance to the coolant treatment and recovery system, the relationship between process design parameters such as the tritium specific activity control value of the primary circuit,water capacity of the coolant treatment and recovery system, and tritium water discharge rate is discussed. Their effects on the tritium discharge amount are studied. The expected amount of the tritium discharged could be 3%~13% less if the tritium specific activity control value of the primary circuit would be raised from 15 000 MB·t^(-1)to 44 000 MB·t^(-1), and could be 46% less if the water capacity of the recovery system would be enlarged to 10 000 t further.

关 键 词：氚 压水堆 系统设计 氚排放量 

分 类 号：TL48[核科学技术—核技术及应用]