摘要
为了提高水冷慢化聚变驱动次临界堆包层中子学分析的精度,在FDS团队自主研发的HENDL3.0/FG(Hybrid Evaluated Nuclear Data Library/Fine Group)细群核数据库基础上,本文采用国际通用应用核数据库加工程序NJOY,设计研发出考虑热中子上散射效应的截面核数据库。利用国际临界安全基准评价实验手册的例题对核数据库的精度进行了测试与校核,验证了数据的可靠性与正确性。同时,采用聚变驱动次临界的聚变裂变混合发电堆(FDS-EM)水冷慢化包层模型对核数据库进行了综合测试与分析,分别从理论及计算分析的角度预测与验证了热中子上散射效应对系统的有效增殖因数、氚增殖率、中子通量密度等参数的影响。
Background： The energy spectrum of water-cooled fusion-driven subcritical system is very complex. It contains large numbers of high-energy neutrons and thermal neutrons. Therefore, conventional database of fission reactors or fast reactors is not appropriate. Purpose： In order to improve the accuracy of the neutronics analysis for subcritical systems with moderated water-cooled blanket, nuclear cross-section data for thermal scattering was developed based on HENDL3.0/FG fine group. Moreover, a conceptual design of fusion-fission hybrid reactor for energy production, named FDS-EM, was tested and analyzed using the database. Methods： The THERMR module of the general application database processing program NJOY was used in developing the library. Critical safety benchmark testing had been carried out to test the reliability of the library. Results： The effectiveness of the nuclear database was validated by the benchmark testing. The influence of thermal up-scatter on kerr, TBR and neutron flux was predicted and verified in theoretical and calculational perspectives. Conclusion： The up-scatter effect is essential in water-cooled fusion-driven subcritical system and this database could be used in the design of future fusion-driven subcritical system.
出处
《核技术》
CAS
CSCD
北大核心
2014年第9期61-68,共8页
Nuclear Techniques
基金
中国科学院战略性先导科技专项(No.XDA03040000)
国家自然科学基金(No.91026004)
中国科学院科技数据资源整合与共享工程项目(No.XXH12504-1-09)
聚变核安全与辐射防护关键技术(No.2014GB112000)资助
作者简介
孙梦萍，女，1991年出生，2012年毕业于中国科技大学，现为中国科学技术大学硕士研究生，研究领域为应用核数据库
通讯作者：胡丽琴，E-mail：liqin．hu@fds．org．cn
