期刊论文

Chen, Z.

中文

核技术

0253-3219

2022

45

8

62-68

10.11889/j.0253-3219.2022.hjs.45.080601

装备预研重点实验室基金项目(No.6142A07200409)、国家自然科学基金(No.12175101)、湖南省教育厅科学研究项目(No.19A422)、大学生创 新创业训练计划项目(No.S202010555036)资助 第一作者：李雷鸣，男，1998年出生，2020年毕业于南华大学，现为硕士研究生，研究领域为反应堆物理 通信作者：陈珍平，E-mail：chzping@usc.edu.cn 收稿日期：2022-03-27，修回日期：2022-04-25 Supported by Fund project of Key Laboratory of Equipment Pre-research (No.6142A07200409), National Natural Science Foundation of China (No. 12175101), Scientific Research Project of Hunan Education Department (No. 19A422), Innovation and Entrepreneurship T raining program for College students (No.S202010555036) Firstauthor:LILeiming,male,bornin1998,graduatedfromUniversityofSouthChinain2020,masterstudent,focusingonnuclearreactorphysics Corresponding author: CHEN Zhenping, E-mail: chzping@usc.edu.cn Received date: 2022-03-27, revised date: 2022-04-25

本校为第一机构

核反应堆结构材料活化分析是核反应堆辐射安全分析的重要内容。传统栅元活化分析方法由于无法描述结构材料内部的非均匀空间活化效应,导致活化源项、活化剂量与真实结果存在较大偏差,有必要开展核反应堆结构材料精细活化分析研究。因此,本文发展了基于网格活化分析的核反应堆结构材料精细活化分析方法,基于蒙特卡罗核粒子输运程序系统(Monte Carlo N-Particle Transport Code System,MCNP)和活化计算程序FISPACT建立了“中子输运-材料活化-活化剂量”耦合的反应堆结构材料精细化活化计算分析程序(MCNP and FISPACT coupled Mesh-based Activation code,MCFisMA),实现了结构材料活化源项精细计算...

[Background] Nuclear reactor structural material activation analysis is an important part of nuclear reactor radiation safety analysis. The traditional cell-based activation analysis method can not describe the non-uniform spatial activation effect inside the structural material cells, resulting in a large deviation between the activation source and the dose results, so it is necessary to carry out the high-resolution activation analysis method for nuclear reactor structural materials. [Purpose] This study aims to develop a high-resolution acti...