固态钍基熔盐堆中^14C的产生及释放探讨  

Production and release of ^(14)C in TMSR-SF1

作　　者：朱兴望 王帅[1] 彭超[1] 何兆忠[1] 陈堃[1] 

机构地区：[1]中国科学院上海应用物理研究所 嘉定园区,上海201800

出　　处：《核技术》2015年第3期81-86,共6页Nuclear Techniques

基　　金：中国科学院战略性先导科技专项项目(No.XDA02050000)资助

摘　　要：熔盐堆作为第四代反应堆论坛推荐的6种候选堆型之一,具有输出温度高、能量密度高、无水冷却等特点。固态钍基熔盐堆(Thorium Molten Salt Reactor with Solid Fuel,TMSR-SF1)堆芯大部分结构材料为石墨,冷却剂杂质及石墨材料中的13C和杂质N、O易被活化产生14C。14C半衰期较长,同其他稳态核素12C、13C一样广泛参与各种复杂的生物循环,在反应堆中受到关注。TMSR-SF1中的14C广泛分布于冷却剂、堆芯石墨结构材料和燃料元件。本文采用输运燃耗耦合方法,应用SCALE6.1的TRITION控制模块对反应堆各区域的14C放射性活度进行计算分析,结果表明,反应堆在正常运行工况下一回路每年产生的14C放射性活度为0.34 TBq,满足现有的压水堆、重水堆管理限值要求。向环境释放的14C主要来自于一回路熔盐中N杂质的活化。Background： As one of the six candidates recommended by the fourth generation reactor forum, Molten Salt Reactor （MSR） owns many features such as high outlet temperature, high energy density, and anhydrous cooling. In the core of the first Thorium Molten Salt Reactor with Solid Fuel （TMSR-SF 1）, most of the structure materials are graphite. ^13C in graphite and the impurities N and O in coolant can be activated to produce ^14C. ^14C has long half-life, it can be involved in various complex biological cycle with other stable nuclides ^12C and ^13C. In TMSR-SF1, ^14C is widely distributed in the coolant, the active core and the structure materials. Purpose： The aim is to study the production and release of ^14C in TMSR-SF 1. Methods： According to the design parameters of TMSR-SF 1, TRITON （Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion） of SCALE6.1 （Standardized Computer Analyses for Licensing Evaluation） was applied for the transport burnup coupled calculation. Results： Computational results show that the radioactivity of ^14C in main loop mainly comes from the activation of N, and the total amount of radioactivity of ^14C in the main loop is 0.34 TBq each year. Conclusion： TMSR-SF1 could meet the current emissions standards of ^14C according to current design parameters.

关 键 词：钍基熔盐堆 ^14C 产生 释放 

分 类 号：TL364[核科学技术—核技术及应用]