动态参数直接统计方法在TMSR-SF1中的应用

朱贵凤; 严睿; 于世和; 康旭忠; 冀锐敏; 周波; 邹杨

doi:10.11889/j.0253-3219.2018.hjs.41.050603

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动态参数直接统计方法在TMSR-SF1中的应用

核能科学与工程 | 更新时间：2021-05-19

- 动态参数直接统计方法在TMSR-SF1中的应用
- An application of direct statistical method for kinetics parameters in TMSR-SF1
- 核技术 2018年41卷第5期文章编号：050603
- 作者机构：
  
  中国科学院上海应用物理研究所嘉定园区上海 201800
- 作者简介：
  
  [ "朱贵凤, 男, 1987年出生, 2015年于中国科学院大学获博士学位, 研究方向为反应堆物理", "ZHU Guifeng, male, born in 1987, graduated from University of Chinese Academy of Sciences with a doctoral degree in 2015, focusing on reactor physics research" ]
  邹杨, E-mail:zouyang@sinap.ac.cn ZOU Yang, E-mail:zouyang@sinap.ac.cn
- 基金信息：
  
  中国科学院战略性先导科技专项(XDA02010000);若干关键问题研究项目(QYZDY-SSW-JSC016)
- DOI：10.11889/j.0253-3219.2018.hjs.41.050603
  中图分类号： TL3
- 收稿日期：2018-01-16，
  
  修回日期：2018-03-28，
  
  纸质出版日期：2018-05-10
- 稿件说明：
移动端阅览
朱贵凤, 严睿, 于世和, 等. 动态参数直接统计方法在TMSR-SF1中的应用[J]. 核技术, 2018,41(5):050603

Guifeng ZHU, Rui YAN, Shihe YU, et al. An application of direct statistical method for kinetics parameters in TMSR-SF1[J]. Nuclear techniques, 2018, 41(5): 050603
朱贵凤, 严睿, 于世和, 等. 动态参数直接统计方法在TMSR-SF1中的应用[J]. 核技术, 2018,41(5):050603 DOI： 10.11889/j.0253-3219.2018.hjs.41.050603.

Guifeng ZHU, Rui YAN, Shihe YU, et al. An application of direct statistical method for kinetics parameters in TMSR-SF1[J]. Nuclear techniques, 2018, 41(5): 050603 DOI： 10.11889/j.0253-3219.2018.hjs.41.050603.

摘要

中子动态参数的准确分析与反应堆的安全特性紧密相关。固态燃料钍基熔盐实验堆（Thorium-based Molten Salt experiment Reactor with Solid Fuel，TMSR-SF1）作为第四代新堆型，采用蒙特卡罗输运程序计算其动态参数更有利于核安全评审。本文基于较通用的蒙特卡罗多粒子输运（Monte Carlo N Particle Transport Code，MCNP）程序，植入了动态参数直接统计方法，用于计算TMSR-SF1中的有效缓发中子份额和有效中子代时间。通过多个ICSBEP（International Criticality Safety Benchmark Evaluation Project）基准题的检验，计算结果与基准题实验误差在±5%以内，证明了该方法的准确性。运用该方法计算得到TMSR-SF1中6组有效缓发中子份额和有效中子代时间随燃耗深度的变化，其计算结果与采用MCNP共轭通量方法所得的数据误差在±3%以内，证明该方法用于TMSR-SF1的动态参数分析是合理可靠的。

Abstract

Background

Kinetics parameters play an important role on reactor safety analysis and dynamic behavior. Thorium-based molten salt experiment reactor with solid fuel (TMSR-SF1) is a new kind of reactor. Using Monte Carlo code to calculate kinetics parameters is in favor of its nuclear safety license.

Purpose

This study aims at realizing the direct statistical calculation of kinetics parameters in Monte Carlo code

and applying this method to obtain the effective delayed neutron fraction and effective neutron generation time of TMSR-SF1.

Methods

We implant the direct statistical method into MCNP (Monte Carlo N Particle Transport Code) code by tallying the fission neutron type and fly time

and verify its accuracy with multiple ICSBEP (International Criticality Safety Benchmark Evaluation Project) benchmark.

Results

The benchmark kinetics parameters calculated by direct statistical method are consistent with experiment measured value (±5% deviation). The effective delayed neutron fraction and effective neutron generation time of TMSR-SF1 we obtained

are close to that of conjugate flux method based on MCNP code.

Conclusion

It is reliable to use direct statistical method to calculate kinetics parameters of TMSR-SF1.

关键词

Keywords

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