聚变驱动次临界堆热中子上散射截面数据库开发及初步应用

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 NuclearData Library／FineGroup）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、...

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Bibliographic Details
Published in核技术 Vol. 37; no. 9; pp. 61 - 68
Main Author 孙梦萍 邹俊 王芳 贾伟 胡丽琴
Format Journal Article
LanguageChinese
Published 中国科学技术大学 合肥230026 2014
中国科学院核能安全技术研究所 合肥230031%中国科学院核能安全技术研究所 合肥230031
Subjects
中子通量密度
有效增殖因数（Keff）
水冷慢化聚变驱动次临界堆
热中子上散射效应
细群核数据库
Effective multiplication factor (keff)
有效增殖因数(keff)
Neutron flux
热中子上散射效应
Fine group data library
中子通量密度
Thermal up-scatter effect
Water-cooled fusion driven subcritical system
水冷慢化聚变驱动次临界堆
细群核数据库
Online AccessGet full text
ISSN0253-3219
DOI10.11889/j.0253-3219.2014.hjs.37.090604

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Summary: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 NuclearData Library／FineGroup）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。
Bibliography: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
ISSN:0253-3219
DOI:10.11889/j.0253-3219.2014.hjs.37.090604