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作 者:王胜哲 刘仕倡 陈义学[1] WANG Shengzhe;LIU Shichang;CHEN Yixue(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China)
机构地区:[1]华北电力大学核科学与工程学院,北京102206
出 处:《核技术》2024年第5期55-70,共16页Nuclear Techniques
基 金:国家自然科学基金委员会―中国工程物理研究院NSAF联合基金(No.U2330117);国家自然科学基金(No.12175067);河北省自然科学基金(No.A2022502008)资助。
摘 要:在聚变反应堆运行过程中,中子活化会导致大量放射性核素的产生,因此活化计算在反应堆的屏蔽设计和辐射安全分析中具有重要作用。本文基于蒙特卡罗粒子输运程序cosRMC的内置燃耗求解器Depth,开发了固定源模式下的内耦合输运-活化耦合计算功能。将该程序应用于中国聚变工程试验堆(Chinese Fusion EngineeringTestingReactor,CFETR)的第一壁(First-wall,FW)材料钢和面向等离子体部件(Plasma-facing Component,PFC)材料钨,分别使用连续能量截面和多群截面进行活化计算,并与活化程序ALARA进行对比验证,发现cosRMC的计算结果与ALARA计算的结果符合良好,初步验证了开发的cosRMC程序输运-活化内耦合计算功能的正确性。与传统蒙特卡罗-活化计算程序的外耦合方式相比,内耦合方式蒙特卡罗不需要把中子能谱传给外部活化程序,而是在蒙特卡罗中子输运过程中嵌入计算活化相关的核素单群反应截面,动态更新中子能谱和材料信息,同时可以使用连续能量截面进行反应率计算,得到与实际问题的几何、能谱相关的反应截面,从而精确地考虑了共振区核截面的影响。[Background]When fusion nuclear reactor is in operation,neutron activation causes a large number of radioisotopes.Activation calculation is a very important step in both of reactor shielding calculation and radiation safety analysis.[Purpose]This study aims to develop the capability of transport-activation coupling calculation for fusion reactor based on the Monte Carlo code cosRMC.[Methods]Firstly,the built-in burnup solver"Depth"of cosRMC was employed to develop transport-activation internal coupling calculation function under fixed source mode with embedded calculation of activation related nuclide single group reaction cross-sections in neutron transport process without the transmission of neutron spectra to external activation programs.Then,the developed code was applied to the activation calculations of the first wall(FW)material steel and plasma facing component(PFC)material tungsten of the Chinese Fusion Engineering Testing Reactor(CFETR)using continuous energy cross-sections and multi group cross-sections,respectively,and calculated results were compared and verified with that of the activation program ALARA.[Results]The comparison results of activation calculation of FW steel and PFC tungsten in CFETR show the consistency between cosRMC-based internal coupling method and ALARA program,which preliminarily verifies the correctness of the transport activation internal coupling calculation function of the developed cosRMC program.[Conclusion]The developed cosRMC-based internal coupling method can dynamically update neutron spectra and material information,and use continuous energy cross-sections for reaction rate calculation,obtaining reaction cross-sections related to the geometry and energy spectra of actual problems,thus accurately considering the influence of resonance zone nuclear cross-sections.
关 键 词:活化计算 聚变堆 固定源 ALARA cosRMC
分 类 号:TL329[核科学技术—核技术及应用]
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