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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| Published in | 核技术 Vol. 37; no. 9; pp. 61 - 68 |
|---|---|
| Main Author | |
| Format | Journal Article |
| Language | Chinese |
| 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 | |
| Online Access | Get full text |
| ISSN | 0253-3219 |
| DOI | 10.11889/j.0253-3219.2014.hjs.37.090604 |
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| Abstract | 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。 |
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| AbstractList | TL61; 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N JOY,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. 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。 |
| Author | 孙梦萍 邹俊 王芳 贾伟 胡丽琴 |
| AuthorAffiliation | 中国科学技术大学,合肥230026 中国科学院核能安全技术研究所,合肥230031 |
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| Author_FL | WANG Fang SUN Mengping ZOU Jun HU Liqin JIA Wei |
| Author_FL_xml | – sequence: 1 fullname: SUN Mengping – sequence: 2 fullname: ZOU Jun – sequence: 3 fullname: WANG Fang – sequence: 4 fullname: JIA Wei – sequence: 5 fullname: HU Liqin |
| Author_xml | – sequence: 1 fullname: 孙梦萍 邹俊 王芳 贾伟 胡丽琴 |
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| Copyright | Copyright © Wanfang Data Co. Ltd. All Rights Reserved. |
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| DOI | 10.11889/j.0253-3219.2014.hjs.37.090604 |
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| DocumentTitleAlternate | Development and preliminary application of thermal neutron cross-section data library for fusion driven subcritical reactor |
| DocumentTitle_FL | Development and preliminary application of thermal neutron cross-section data library for fusion driven subcritical reactor |
| EndPage | 68 |
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| Issue | 9 |
| Keywords | 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 |
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| Notes | 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 |
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| PublicationTitleAlternate | Nuclear Techniques |
| PublicationTitle_FL | Nuclear Techniques |
| PublicationYear | 2014 |
| Publisher | 中国科学技术大学 合肥230026 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 |
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| SubjectTerms | 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 |
| Title | 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 |
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