次临界能源堆用多群截面库的研制与校验

基金项目:

次临界能源堆物理设计及总体概念研究(2010GB111001)

Development and Validation of Multi-Group Cross-Section Library for Subcritical Energy Reactor

1. Department of Engineering Physics, Tsinghua University, Beijing, 100084, China;
2. Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, Sichuan, 621900, China;
3. Institute of Applied Physics and Computational Mathematics, Beijing, 100088, China

摘要: 采用NJOY程序制作187群多群截面,使用输运程序ANISN计算铀球临界基准题和铀球水腔模型,对该多群截面库临界计算、反应率、中子能谱计算进行数值校验。将该多群截面应用于次临界能源堆多层球壳模型计算,计算结果与连续能量蒙特卡罗程序MCNP5的结果进行比较。结果表明,该多群截面库制作正确,可用于次临界能源堆物理计算,能够正确给出反应率值和中子能谱。
- 次临界能源堆 /
- 多群截面 /
- 多层球壳模型
Abstract: As the fusion-driven subcritical energy reactor has wide and complex energy spectrum,multigroup cross-section library needs to be developed for its design requirement.A 187-group neutron cross-section library is developed by using NJOY code.With transport code ANISN,enriched uranium critical sphere benchmarks and uranium sphere model with water cavity are calculated to validate the multigroup cross-section library Multi-layer shell model of subcritical energy reactor is calculated,and the results are compared with MCNP5.The results show that the multigroup cross-section library is correct and can be used for subcritical energy reactor design,and the reaction rates and neutron spectra in subcritical energy reactor can be calculated as well.
- Subcritical energy reactor /
- Multigroup cross-section /
- Multi-layer sphere model