基于蒙特卡罗程序的AP1000反应堆堆芯布置方案的模拟

张陆雨; 王志敏; 白怀勇; 陈金象; 张国辉

doi:10.11889/j.0253-3219.2017.hjs.40.040604

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基于蒙特卡罗程序的AP1000反应堆堆芯布置方案的模拟

核能科学与工程 | 更新时间：2021-05-19

- 基于蒙特卡罗程序的AP1000反应堆堆芯布置方案的模拟
- Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code
- 核技术 2017年40卷第4期文章编号：040604
- 作者机构：
  
  北京大学核物理与核技术国家重点实验室物理学院重离子物理研究所北京 100871
- 作者简介：
  
  [ "张陆雨, 男, 1991年出生, 2014年毕业于南华大学, 现为硕士研究生, 从事中子物理与反应堆物理研究", "ZHANG Luyu, male, born in1991, graduated from University of South China in 2014, master student, focusing on research of the neutron physics and reactor physics" ]
  张国辉, E-mail:guohuizhang@pku.edu.cn ZHANG Guohui, E-mail:guohuizhang@pku.edu.cn
- 基金信息：
  
  国家自然科学基金(11475007)
- DOI：10.11889/j.0253-3219.2017.hjs.40.040604
  中图分类号： TL32
- 收稿日期：2016-12-28，
  
  修回日期：2017-02-16，
  
  纸质出版日期：2017-04-10
- 稿件说明：
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张陆雨, 王志敏, 白怀勇, 等. 基于蒙特卡罗程序的AP1000反应堆堆芯布置方案的模拟[J]. 核技术, 2017,40(4):040604

Luyu ZHANG, Zhimin WANG, Huaiyong BAI, et al. Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code[J]. Nuclear techniques, 2017, 40(4): 040604
张陆雨, 王志敏, 白怀勇, 等. 基于蒙特卡罗程序的AP1000反应堆堆芯布置方案的模拟[J]. 核技术, 2017,40(4):040604 DOI： 10.11889/j.0253-3219.2017.hjs.40.040604.

Luyu ZHANG, Zhimin WANG, Huaiyong BAI, et al. Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code[J]. Nuclear techniques, 2017, 40(4): 040604 DOI： 10.11889/j.0253-3219.2017.hjs.40.040604.

摘要

AP1000是美国西屋公司研发的大型压水反应堆，采用先进的非能动安全系统。AP1000反应堆有两种堆芯燃料布置方案：D19和Adv。结合两种设计方案的优点提出了一种新的堆芯燃料布置方案。利用MCNP6（Monte Carlo N-particle 6）程序对D19堆芯和新方案堆芯的首循环进行建模，并主要计算了新堆芯的核设计参数随燃耗的变化。结果表明，新堆芯在首循环寿期内满足AP1000的主要核设计准则。通过大规模并行计算表明，带燃耗计算功能的蒙特卡罗程序MCNP6能够在堆芯设计工作中发挥很好的参考作用。

Abstract

Background

AP1000

developed by the Westinghouse

is a pressurized water reactor with advanced passive safety systems. Two core fuel configuration schemes

D19 and Adv

are available for the AP1000.

Purpose

This study aims to design a new core configuration scheme for AP1000

and compare it with D19 scheme by using Monte Carlo code

Methods

First of all

a new core configuration scheme that combines the advantages of the D19 and Adv schemes was put forwarded. Then the D19 core scheme and the new core scheme were modeled by using the MCNP6 code. Finally

main nuclear design parameters of the new core scheme were calculated according to the varied fuel burnup.

Results

The results indicate that the main physical parameters of the new scheme agree well with the AP1000 nuclear design criterion over the lifetime period of the first cycle.

Conclusions

With the function of burnup calculation

Monte Carlo code MCNP6 play a good role in the reference process of core physical design by massively parallel computing.

关键词

Keywords

references

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