Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark

Hongfei LIU; Binhang ZHANG; Shu ZHANG; Guangyao SUN; Lijuan HAO; Jing SONG; Pengcheng LONG

doi:10.11889/j.0253-3219.2016.hjs.39.040604

您当前的位置：

首页 >

文章列表页 >

Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark

更新时间：2021-05-25

- Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark
- NUCLEAR TECHNIQUES Vol. 39, Issue 4, Article number: 040604(2016)
- 作者机构：
  
  中国科学院核能安全技术研究所中国科学院中子输运理论与辐射安全重点实验室合肥 230031
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.040604
  CLC： TL329.2
- Received：04 January 2016，
  
  Revised：02 February 2016，
  
  Accepted：2016-02-02，
  
  Published：25 April 2016
- 稿件说明：
移动端阅览
Hongfei LIU, Binhang ZHANG, Shu ZHANG, et al. Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark[J]. Nuclear techniques, 2016, 39(4): 040604
DOI：

Hongfei LIU, Binhang ZHANG, Shu ZHANG, et al. Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark[J]. Nuclear techniques, 2016, 39(4): 040604 DOI： 10.11889/j.0253-3219.2016.hjs.39.040604.

摘要

基于国际经典的压水堆全堆芯Hoogenboom基准模型

对超级蒙特卡罗核计算仿真软件系统SuperMC(Super Monte Carlo Simulation Program for Nuclear and Radiation Process)进行了校验。对有效增殖因数

eff

、功率等反应堆关键参数进行了计算与正确性校验

对并行效率进行了分析。结果显示

SuperMC的计算结果与MCNP(Monte Carlo N Particle Transport Code)吻合较好

在使用640核计算时并行效率高达98.7%

初步验证了SuperMC在全堆芯计算中的准确性及高效性。

Abstract

Background:

A full core Hoogenboom benchmark reactor model was proposed by Hoogenboom and Martin to monitor the increase in performance of Monte Carlo calculations of a full-size power reactor core over the coming years.

Purpose:

The correctness and computing performance of SuperMC(Super Monte Carlo Simulation Program for Nuclear and Radiation Process) was tested.

Methods:

The

eff

and power distribution were calculated and compared with MCNP(Monte Carlo N Particle Transport Code)

and parallel efficiency was analyzed.

Results:

The SuperMC calculation results agreed well with those of MCNP

with the parallel efficiency reaching up to 98.7% by using 640 processors.

Conclusion:

Testing results validated the accuracy and efficiency of SuperMC in full reactor core calculation.

关键词

Keywords

references

Smith K . Reactor core methods .

Hoogenboom J E , Martin W R . A proposal for a benchmark to monitor the performance of detailed Monte Carlo calculation of power densities in a full size reactor core . Saratoga Springs, NY:Proceedings ANS Mathematics & Computation Division Topical Meeting , 2009 .

Wu Y , Song J , Zheng H , . CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC . Annals of Nuclear Energy , 2015 . 82 161 - 168 .

Wu Y , FDS Team . CAD-based interface programs for fusion neutron transport simulation . Fusion Engineering and Design , 2009 . 84 ( 7-11 ): 1987 - 1992 .

Wu Y , Xie Z , Fischer U . A discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries . Nuclear Science Engineering , 1999 . 133 ( 3 ): 350 - 357 .

Zhang B H , Song J , Sun G Y , . Criticality validation of SuperMC with ICSBEP . Annals of Nuclear Energy , 2016 . 87 494 - 499 .

Wu Y , FDS Team . Conceptual design activities of FDS series fusion power plants in China . Fusion Engineering and Design , 2006 . 81 2713 - 2718 .

Wu Y , FDS Team . Conceptual design and testing strategy of a dual functional lithium-lead test blanket module in ITER and EAST . Nuclear Fusion , 2007 . 47 ( 11 ): 1533 - 1539 .

Wu Y , FDS Team . Design analysis of the China dual-functional lithium lead(DFLL) test blanket module in ITER . Fusion Engineering and Design , 2007 . 82 1893 - 1903 .

Wu Y , FDS Team . Conceptual design of the China fusion power plant FDS-Ⅱ . Fusion Engineering and Design , 2008 . 83 1683 - 1689 .

汪晖 , 宋婧 , 孙光耀 , . 基于钠冷快堆BN-600的SuperMC基准校验分析 . 原子能科学技术 , 2015 . 49 .

WANG Hui , SONG Jing , SUN Guangyao , . Benchmarking of SuperMC based on sodium cooled fast reactor BN-600 . Atomic Energy Science and Technology , 2015 . 49 .

Hoogenboom J E , Martin W R , Petrovic B . Monte Carlo performance benchmark for detailed power density calculation in a full size reactor core, benchmark specifications revision 1 .

曾勤 , 邹俊 , 许德政 , . 315中子/42光子耦合细群核数据库HENDL3 .

ZENG Qin , ZOU Jun , XU Dezheng , . Development of fine-group(315n/42γ) cross section library ENDL3 .

Zou J , He Z Z , Zeng Q , . Development and testing of multi-group library with correction of self-shielding effects in fusion-fission hybrid reactor . Fusion Engineering and Design , 2010 . 85 1587 - 1590 .

Zhang S . Hierarchical geometry tree-based method for scoring massive tallies in Monte Carlo particle transport calculation .

Hoogenboom J E , Petrovic B , Martin W R . Monte Carlo computational performance benchmark . Paris:Workshop at SNA+MC2013, October 27 , 2013 .

Forrest B , Brown J . MCNP5 parallel processing workshop . Gatlinburg, TN:ANS Mathematics & Computation Topical Meeting, April 11 , 2003 .

Romano P K , Forget B . Parallel fission bank algorithms in Monte Carlo criticality calculation . Nuclear Science and Engineering , 2012 . 170 ( 2 ): 125 - 135 .

李静 , 宋婧 , 龙鹏程 , . 基于双向遍历的蒙特卡罗临界计算并行方法 . 核技术 , 2015 . 38 ( 6 ): 060602 .

LI Jing , SONG Jing , LONG Pengcheng , . Parallel computing method of Monte Carlo criticality calculation based on bi-directional traversal . Nuclear Techniques , 2015 . 38 ( 6 ): 060602 .

Romano P K , Siegel A R , Forget B , . Data decomposition of Monte Carlo particle transport simulations via tally servers . Journal of Computational Physics , 2013 . 252 20 - 36 .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Simulated analysis of the influence factor of the neutron response in neutron shielding testing system

Parallel computing method of Monte Carlo criticality calculation based on bi-directional traversal

Development of the neutronics calculation module of neutronics and thermal hydraulic calculation program NECP-Panda for pebble-bed high temperature gas-cooled reactor

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

Calculation methods of parameters in α particle measurement

Related Author

王连才

曾心苗

GUO Guangshui

ZHANG Long

MENG Xianfang

CAO Ke

QIN Peizhong

LI Jing

Related Institution

Beijing Key Laboratory of New Radiation Materials, Beijing Radiation Application Research Center

School of Mathematics, Hefei University of Technology

Huaneng Nuclear Energy Technology Research Institute

Xi'an Jiaotong University

School of Nuclear Science and Engineering, Shanghai Jiao Tong University

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