Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code

Luyu ZHANG; Zhimin WANG; Huaiyong BAI; Jinxiang CHEN; Guohui ZHANG

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

您当前的位置：

首页 >

文章列表页 >

Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code
- NUCLEAR TECHNIQUES Vol. 40, Issue 4, Article number: 040604(2017)
- 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：
- 基金信息：
  
  National Natural Science Foundation of China
- DOI：10.11889/j.0253-3219.2017.hjs.40.040604
  CLC： TL32
- Received：28 December 2016，
  
  Revised：16 February 2017，
  
  Published：10 April 2017
- 稿件说明：
移动端阅览
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：

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

T L Schulz . Westinghouse AP1000 advanced passive plant . Nuclear Engineering and Design , 2006 . 236 1547 - 1549 . DOI: 10.1016/j.nucengdes.2006.03.049 http://doi.org/10.1016/j.nucengdes.2006.03.049 .

陈德锋. 基于MCNP程序的AP1000反应堆屏蔽分析研究[D]. 哈尔滨: 哈尔滨工程大学核科学与技术学院, 2013.

CHEN Defeng. Shielding analysis of AP1000 reactor by MCNP code[D]. Harbin: College of Nuclear Seience and Engineering, Harbin Engineering University, 2013.

P F Wang , J S Wan , Z Chen , . Dynamic simulation and study of Mechanical Shim (MSHIM) core control strategy for AP1000 reactor . Annals of Nuclear Energy , 2014 . 72 49 - 51 . DOI: 10.1016/j.anucene.2014.04.023 http://doi.org/10.1016/j.anucene.2014.04.023 .

J F Robert . AP1000 core design with 50% MOX loading . Annals of Nuclear Energy , 2009 . 36 324 - 325 . DOI: 10.1016/j.anucene.2008.11.022 http://doi.org/10.1016/j.anucene.2008.11.022 .

李雪松 . 浅析AP1000首炉堆芯装载设计对核电厂运行的影响 . 中国核科学技术进展报告 , 2009 . 1 1037 - 1040 . http://cpfd.cnki.com.cn/Article/CPFDTOTAL-EGVD200911003097.htm .

Xuesong LI . Discussion of the effects of AP1000 first core loading pattern design on nuclear power plant operation . Progress Report on China Nuclear Science & Technology , 2009 . 1 1037 - 1040 . http://cpfd.cnki.com.cn/Article/CPFDTOTAL-EGVD200911003097.htm .

姚增华 . 评AP1000堆芯设计 . 核动力工程 , 2014 . 35 ( S1 ): 75 - 79 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG2014S1021.htm .

Zenghua YAO . Review on core design of AP1000 . Nuclear Power Engineering , 2014 . 35 ( S1 ): 75 - 79 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG2014S1021.htm .

X-5 Monte Carlo Team. MCNP-MCNP6TM user's manual[R]. Version 1.0. Report LA-CP-13-00634, Los Alamos National Laboratory, 2013.

薛春 , 张海青 , 朱智勇 , . 组件型熔盐堆燃料组件的设计研究 . 核技术 , 2016 . 39 ( 9 ): 090602 DOI: 10.11889/j.0253-3219.2016.hjs.39.090602 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.090602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract649.shtml .

Chun XUE , Haiqing ZHANG , Zhiyong ZHU , . Design of fuel assembly for molten-salt-cooled reactors . Nuclear Techniques , 2016 . 39 ( 9 ): 090602 DOI: 10.11889/j.0253-3219.2016.hjs.39.090602 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.090602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract649.shtml .

魏强林 , 刘义保 , 杨波 , . 控制黑棒和灰棒对AP1000反应堆 K eff 值影响的M-C模拟 . 科学技术与工程 , 2013 . 13 ( 8 ): 2074 - 2078 .

Qianglin WEI , Yibao LIU , Bo YANG , . M-C simulation on K eff value for control and gray rod effect in AP1000 reactor . Science Technology and Engineering , 2013 . 13 ( 8 ): 2074 - 2078 .

林诚格 . 非能动安全先进压水堆核电技术 , : 北京原子能出版社 , 2010 . 101 - 117 . http://www.cnki.com.cn/Article/CJFDTOTAL-SYQY201603027.htm .

Chengge LIN . The passive security advanced pressurized water reactor nuclear power technology , : Beijing Atomic Energy Press , 2010 . 101 - 117 . http://www.cnki.com.cn/Article/CJFDTOTAL-SYQY201603027.htm .

T Guo , J W Hu , S D Mao , . Evaluation of the pressure-volume-temperature (PVT) data of water from experiments and molecular simulations since 1990 . Physics of the Earth and Planetary Interiors , 2015 . 245 88 - 90 . DOI: 10.1016/j.pepi.2015.06.001 http://doi.org/10.1016/j.pepi.2015.06.001 .

S H Yang , Y X Chen , Y Hu , . Evaluation of fast neutron inserted to RPV materials and management of RPV lifetime for PWR power plant . Advanced Materials Research , 2012 . 413 514 - 516 . DOI: 10.4028/www.scientific.net/AMR.413.514 http://doi.org/10.4028/www.scientific.net/AMR.413.514 .

魏述平 , 李兰 , 程诗思 , . 含MOX燃料堆芯与传统堆芯的辐射特性对比研究 . 核技术 , 2015 . 38 ( 10 ): 100601 DOI: 10.11889/j.0253-3219.2015.hjs.38.100601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.100601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract485.shtml .

Shuping WEI , Lan LI , Shisi CHENG , . Comparison of irradiation characteristics between the reactor core with the MOX fuel and the traditional core . Nuclear Techniques , 2015 . 38 ( 10 ): 100601 DOI: 10.11889/j.0253-3219.2015.hjs.38.100601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.100601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract485.shtml .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Development and validation of LightAB: a new light general-purpose activation-burnup program

Analysis on key factors of ²⁵²Cf production by irradiation of high flux fast neutron research reactor

Related Author

LIU Langtao

PAN Qingquan

ZHAO Qingfei

ZHANG Zhenyu

YANG Hongyi

WU Mingyu

YANG Yong

LU Peiyibin

Related Institution

School of Nuclear Science and Engineering, Shanghai Jiao Tong University

China Institute of Atomic Energy

AI问答

Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
Tel：021-39194977 Email：LHB@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
Total Visits：881268 Visits Today：795

⁰