摘要
熔盐堆是第四代国际核能论坛推荐的6种先进四代堆之一,具有良好的中子经济性、固有安全性、可在线后处理等特点。基于熔盐燃料和冷却剂的流动性,熔盐堆可对堆内产生的放射性气体进行在线移除,周期性地从熔盐泵中除去135Xe和85Kr等中子毒物,以提高燃料循环过程中的中子经济性。目前主要的源项计算软件并不完全适用于熔盐堆在线除气情况下的源项计算,为了解熔盐堆在线处理情况下的源项分布,为熔盐堆辐射防护设计提供参考依据,并验证熔盐堆在线处理情况下源项计算方法的可行性和计算结果的可靠性,采用实际运行过的美国橡树岭国家实验室熔盐实验堆(Molten Salt Reactor Experiment,MSRE)参数,应用自主开发的PostTRITON程序计算了含在线处理情况下的源项,分析了熔盐堆裂变产物产额及氚的产生情况,并应用SCALE5.1软件包中TRITON模块计算了无在线处理情况下的源项,分析了数据偏差的原因,并与橡树岭国家实验室的计算数据进行了比较,计算结果在±8%的范围内符合一致。通过本研究,验证了在线处理下熔盐堆源项计算方法的可行性和结果的可靠性,可为熔盐堆的辐射防护设计提供重要的参考。
Background： Molten salt reactor （MSR）, a candidate of the Generation IV reactors, has the advantages of inherent safety, on-line refueling and good neutron economy. Neutrons absorption of the poisons such as 135Xe and 85Kr would affect the reactivity of the reactor. As a result, on-line processing is required to remove gases when the reactor is run. Most of the computation codes that are available for calculation of the source terms have not taken liquid fuel flow and online reprocessing into account. Purpose： This paper attempts to analyze the impacts of on-line removing radioactive gases on the source terms and provide reliable source terms for the radiation protection of MSR. Methods： Source terms of the Molten Salt Reactor Experiment （MSRE）, - originally developed at the Oak Ridge National Laboratory （ORNL） of USA, with/without on-line processing are calculated by using self-developed code PostTRITON and the TRITON module of the SCALE5.1 package. Results： The productions of the radioactivity of fission products and tritium were calculated for MSRE, and compared with the data given by ORNL. The results were consistent within the error of ±8%. Conclusion： The calculation method of the source terms for the MSRE with on-line removing radioactive gases is feasible and reliable to provide important data for the radiation protection of MSRs.
出处
《核技术》
CAS
CSCD
北大核心
2014年第2期62-68,共7页
Nuclear Techniques
基金
中国科学院战略性先导科技专项(XDA02005002
XDA02005004)资助
