基于参数的可视化裂变堆芯蒙特卡罗自动建模方法

甘佺; 吴斌; 宋婧; 程梦云; 胡丽琴

doi:10.11889/j.0253-3219.2016.hjs.39.060501

您当前的位置：

首页 >

文章列表页 >

基于参数的可视化裂变堆芯蒙特卡罗自动建模方法

核物理、交叉学科研究 | 更新时间：2021-05-24

- 基于参数的可视化裂变堆芯蒙特卡罗自动建模方法
- Rapid parameter-based and visual Monte Carlo modeling method of fission reactor core
- 核技术 2016年39卷第6期文章编号：060501
- 作者机构：
  
  1.中国科学技术大学核科学技术学院合肥 230027
  2.中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室合肥 230031
- 作者简介：
  
  [ "甘佺，男，1988年出生，2009年毕业于沈阳师范大学，现为博士研究生，从事辐射输运自动建模方法，核科学与技术专业", "GAN Quan, male, born in 1988, graduated from Shenyang Normal University in 2009, doctor student, engaged in radiation transport automatic modeling method, major in nuclear science and technology" ]
  胡丽琴，E-mail: liqin.hu@fds.org.cn HU Liqin, E-mail: liqin.hu@fds.org.cn
- 基金信息：
  
  国家自然科学基金(11305203);国家自然科学基金(11405204);国家自然科学基金(91026004);国家自然科学基金(11305205);国家磁约束核聚变能发展研究专项(2014GB112001)
- DOI：10.11889/j.0253-3219.2016.hjs.39.060501
  中图分类号： TL329.2
- 收稿日期：2016-02-22，
  
  修回日期：2016-03-21，
  
  纸质出版日期：2016-06
- 稿件说明：
移动端阅览
甘佺, 吴斌, 宋婧, 等. 基于参数的可视化裂变堆芯蒙特卡罗自动建模方法[J]. 核技术, 2016,39(6):060501

Quan GAN, Bin WU, Jing SONG, et al. Rapid parameter-based and visual Monte Carlo modeling method of fission reactor core[J]. Nuclear techniques, 2016, 39(6): 060501
甘佺, 吴斌, 宋婧, 等. 基于参数的可视化裂变堆芯蒙特卡罗自动建模方法[J]. 核技术, 2016,39(6):060501 DOI： 10.11889/j.0253-3219.2016.hjs.39.060501.

Quan GAN, Bin WU, Jing SONG, et al. Rapid parameter-based and visual Monte Carlo modeling method of fission reactor core[J]. Nuclear techniques, 2016, 39(6): 060501 DOI： 10.11889/j.0253-3219.2016.hjs.39.060501.

摘要

蒙特卡罗程序已经广泛应用在裂变反应堆设计和验证过程中

快速获得高效的计算模型可以有效缩短反应堆的设计周期。本研究提出并实现了一种裂变堆芯快速蒙特卡罗建模的方法

该方法基于参数可视化和层次化两种建模思想快速构建出精细裂变堆芯计算机辅助设计(Computer Aided Design

CAD)模型且将其快速转换成蒙特卡罗计算模型

同时采用一种新的堆芯分段管理方法实现了大规模裂变堆模型流畅交互。基于此方法快速构建了加速器驱动次临界反应堆(Accelerator Driven Sub-critical System

ADS)的精细堆芯模型

通过与蒙特卡罗程序计算的参考结果进行对比

证明了此建模方法的高效性和可靠性。

Abstract

Background

The Monte Carlo (MC) method is widely used in fission reactor design

because of its stronger geometry adaptability and the precise calculation result. The high-fidelity full core simulation demands for detailed fission reactor models

which is hard to build by manual and the conventional Computer Aided Design (CAD)-based modeling method.

Purpose

In order to support the rapid design of fission reactor core with MC method

and generate the detailed MC calculation models

a parameter-based and visual MC modeling method was developed in this study.

Method

The method can create the detailed CAD models and convert them into MC models in a high-efficiency way. Meanwhile

the huge amounts of models in fission reactor core can be managed by different segments for supporting smooth interactions.

Result

Furthermore

the method was validated by the test of creating the Accelerator Driven Sub-critical System (ADS) reactor models

and the results were agree very well by comparing the reference models.

Conclusion

Depending on the test

the detailed fission models were created more conveniently than conventional method and the numerical calculation results proved the accuracy of the new method.

关键词

Keywords

references

Smith K, Forget B. Challenges in the development of high-fidelity LWR core neutronics tools[C]. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Idaho, USA, May 5-9, 2013

P Vaz . Monte Carlo methods and techniques status and prospect for future evolution . Applied Radiation and Isotopes , 2010 . 68 ( 4 ): 536 - 541 . DOI: 10.1016/j.apradiso.2009.10.020 http://doi.org/10.1016/j.apradiso.2009.10.020 .

Horelik N, Herman B. Benchmark for evaluation and validation of reactor simulations (BEAVRS)[C]. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, Sun Valley, Idaho, USA, May 5-9, 2013

吴宜灿 , 李莹 , 卢磊 , . 蒙特卡罗粒子输运计算自动建模程序系统的研究与发展 . 核科学与工程 , 2006 . 26 ( 1 ): 20 - 27 . DOI: 10.3321/j.issn:0258-0918.2006.01.004 http://doi.org/10.3321/j.issn:0258-0918.2006.01.004 .

Yican WU , Ying LI , Lei LU , . Research and development of the automatic modeling system for Monte Carlo particle transport simulation . Nuclear Science and Engineering , 2006 . 26 ( 1 ): 20 - 27 . DOI: 10.3321/j.issn:0258-0918.2006.01.004 http://doi.org/10.3321/j.issn:0258-0918.2006.01.004 .

吴宜灿 , 胡丽琴 , 罗月童 , . 先进核能系统设计分析软件与数据库研发进展 . 核科学与工程 , 2010 . 30 ( 1 ): 60 - 69 .

Yican WU , Liqin HU , Yuetong LUO , . Development of design and analysis software for advanced nuclear systems . Nuclear Science and Engineering , 2010 . 30 ( 1 ): 60 - 69 .

Y C Wu , Team FDS . CAD-based interface programs for fusion neutron transport simulation . Fusion Engineering and Design , 2009 . 84 ( 7-11 ): 1987 - 1992 . DOI: 10.1016/j.fusengdes.2008.12.041 http://doi.org/10.1016/j.fusengdes.2008.12.041 .

吴宜灿 , 李静惊 , 李莹 . 大型集成多功能中子学计算与分析系统VisualBUS的研究与发展 . 核科学与工程 , 2007 . 27 ( 4 ): 365 - 373 . DOI: 10.3321/j.issn:0258-0918.2007.04.014 http://doi.org/10.3321/j.issn:0258-0918.2007.04.014 .

Yican WU , Jingjing LI , Ying LI . An integrated multi-functional neutronics calculation and analysis code system:VisualBUS . Nuclear Science and Engineering , 2007 . 27 ( 4 ): 365 - 373 . DOI: 10.3321/j.issn:0258-0918.2007.04.014 http://doi.org/10.3321/j.issn:0258-0918.2007.04.014 .

Y Li , L Lu , A P Ding , . Benchmarking of MCAM4 . Fusion Engineering and Design , 2007 . 82 ( 15 ): 2861 - 2866 . DOI: 10.1016/j.fusengdes.2007.02.022 http://doi.org/10.1016/j.fusengdes.2007.02.022 .

Y C Wu , Team FDS . Conceptual design of the China fusion power plant FDS-Ⅱ . Fusion Engineering and Design , 2008 . 83 ( 10-12 ): 1683 - 1689 . DOI: 10.1016/j.fusengdes.2008.06.048 http://doi.org/10.1016/j.fusengdes.2008.06.048 .

Y C Wu , Team FDS . Conceptual design activities of FDS series fusion power plants in China . Fusion Engineering and Design , 2006 . 81 ( 23-24 ): 2713 - 2718 . DOI: 10.1016/j.fusengdes.2006.07.068 http://doi.org/10.1016/j.fusengdes.2006.07.068 .

Y C Wu , Team FDS . 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 .

Y C Wu , S Zheng , X Zhu , . Conceptual design of the fusion-driven subcritical system FDS-I . Fusion Engineering and Design , 2006 . 81 ( 8-14 ): 1305 - 1311 . DOI: 10.1016/j.fusengdes.2005.10.015 http://doi.org/10.1016/j.fusengdes.2005.10.015 .

Y C Wu , Team FDS . Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER . Fusion Engineering and Design , 2007 . 82 ( 15 ): 1893 - 1903 . DOI: 10.1016/j.fusengdes.2007.08.012 http://doi.org/10.1016/j.fusengdes.2007.08.012 .

Y C Wu , J Q Jiang , M H Wang , . A fusion-driven subcritical system concept based on viable technologies . Nuclear Fusion , 2011 . 51 ( 10 ): 103036 .

Y C Wu , Team FDS . Design status and development strategy of China liquid lithium-lead blankets and related material technology . Journal of Nuclear Materials , 2007 . 367-370 1410 - 1415 . DOI: 10.1016/j.jnucmat.2007.04.031 http://doi.org/10.1016/j.jnucmat.2007.04.031 .

J Song , G Y Sun , Z P Chen , . Benchmarking of CAD-based SuperMC with ITER benchmark model . Fusion Engineering and Design , 2014 . 89 ( 11 ): 2499 - 2503 . DOI: 10.1016/j.fusengdes.2014.05.003 http://doi.org/10.1016/j.fusengdes.2014.05.003 .

R Jain , T J Tautges . Generating unstructured nuclear reactor core meshes in parallel . Procedia Engineering , 2014 . 82 351 - 364 . DOI: 10.1016/j.proeng.2014.10.396 http://doi.org/10.1016/j.proeng.2014.10.396 .

吴宜灿 , 俞盛朋 , 程梦云 , . 多物理耦合分析自动建模软件SuperMC/MCAM5.2设计与实现 . 原子能科学技术 , 2015 . 49 ( z1 ): 1 - 6 . DOI: 10.7538/yzk.2015.49.S0.0001 http://doi.org/10.7538/yzk.2015.49.S0.0001 .

Yican WU , Shengpeng YU , Mengyun CHENG , . Design and implementation of multi-physics coupling analysis modeling program SuperMC/MCAM5.2 . Atomic Energy Science and Technology , 2015 . 49 ( z1 ): 1 - 6 . DOI: 10.7538/yzk.2015.49.S0.0001 http://doi.org/10.7538/yzk.2015.49.S0.0001 .

Donovan T, Tyburski L. Geometrics representations in the developmental Monte Carlo transport code MC21[R]. New York, USA:Knolls Atomic Power Laboratory, 2006. DOI: http://dx.doi.org/10.1051/snamc/201402505

Geant4 Collaboration. Geant4 user's guide for applications developers[OL]. 2015. http://geant4.web.cern.ch http://geant4.web.cern.ch

Nease R N, Millman D L, Griesheimer D P, et al. Geometric templates for improved tracking performance in Monte Carlo codes[C]. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, Paris, France, October 27-31, 2013

Brown F B. Fundamentals of Monte Carlo transport[R]. USA:Los Alamos National Laboratory, 2004

X-5 Monte Carlo Team. MCNP-a general Monte Carlo N-particle transport code[R]. Version 5. Los Alamos National Laboratory, 2003

吴宜灿 , 柏云清 , 宋勇 , . 中国铅基反应堆概念设计研究 . 核科学与工程 , 2014 . 34 ( 2 ): 201 - 208 .

Yican WU , Yunqing BAI , Yong SONG , . Conceptual design of China Lead-based Research Reactor CLEAR-I . Nuclear Science and Engineering , 2014 . 34 ( 2 ): 201 - 208 .

Y C Wu , Y Q Bai , Y Song , . Development strategy and conceptual design of China Lead-based Research Reactor . Annals Nuclear Energy , 2016 . 87 ( 2 ): 511 - 516 . DOI: 10.1016/j.anucene.2015.08.015 http://doi.org/10.1016/j.anucene.2015.08.015 .

Y C Wu , J Song , H Q Zheng , . CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC . Annals of Nuclear Energy , 2015 . 82 161 - 168 . DOI: 10.1016/j.anucene.2014.08.058 http://doi.org/10.1016/j.anucene.2014.08.058 .

浏览量

下载量

CSCD

文章被引用时，请邮件提醒。

提交

工具集

关联资源

球床式高温气冷堆物理热工计算程序NECP-Panda中子学计算模块研制

轻量化通用活化-燃耗分析程序LightAB开发与验证

α粒子测量中的参数计算方法研究

微型反应堆高速撞击下核临界安全的初步分析

基于医用质子直线注入器的超高剂量率细胞辐照实验平台的设计