On-the-fly Doppler broadening method based on piecewise Gauss quadrature for generating neutron cross section

Rui CHEN; Lijuan HAO; Jing SONG; Bin WU; Peng HE

doi:10.11889/j.0253-3219.2017.hjs.40.040503

您当前的位置：

首页 >

文章列表页 >

On-the-fly Doppler broadening method based on piecewise Gauss quadrature for generating neutron cross section

NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH | 更新时间：2021-05-19

- On-the-fly Doppler broadening method based on piecewise Gauss quadrature for generating neutron cross section
- NUCLEAR TECHNIQUES Vol. 40, Issue 4, Article number: 040503(2017)
- 作者机构：
  
  1.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
  2.中国科学技术大学合肥 230027
- 作者简介：
- 基金信息：
  
  National Natural Science Foundation of China;National Natural Science Foundation of China
- DOI：10.11889/j.0253-3219.2017.hjs.40.040503
  CLC： TL329.2
- Received：08 December 2016，
  
  Revised：26 December 2016，
  
  Published：10 April 2017
- 稿件说明：
移动端阅览
Rui CHEN, Lijuan HAO, Jing SONG, et al. On-the-fly Doppler broadening method based on piecewise Gauss quadrature for generating neutron cross section[J]. Nuclear techniques, 2017, 40(4): 040503
DOI：

Rui CHEN, Lijuan HAO, Jing SONG, et al. On-the-fly Doppler broadening method based on piecewise Gauss quadrature for generating neutron cross section[J]. Nuclear techniques, 2017, 40(4): 040503 DOI： 10.11889/j.0253-3219.2017.hjs.40.040503.

摘要

反应堆运行过程中温度不断变化，在模拟中常采用在线多普勒展宽方法生成各种温度下的中子核截面。已有的在线截面生成方法中，SIGMA1方法精度较高，但由于其使用了误差函数及泰勒级数展开方法，截面的生成效率偏低。本文基于FDS团队自主研发的超级蒙特卡罗核模拟软件系统SuperMC，针对不同能段截面的特点，发展了基于分段高斯积分的在线多温度核截面生成方法，在多普勒展宽共振峰较密集的区域使用高斯-厄米特积分方法，在低能区域使用高斯-勒让德积分方法，在保证核截面精度的同时提高了截面生成效率。通过典型核素截面的对比以及临界安全基准例题与多普勒反应性系数基准例题的测试，本文方法与SIGMA1方法相比平均计算效率提高5倍以上，且展宽温度越高，效率提升越明显。证明了该方法能够快速并准确地生成各种温度下的中子核截面，可用于反应堆多物理耦合计算。

Abstract

Background

As temperatures are constantly changing in nuclear reactor operation

on-the-fly Doppler broadening methods are commonly adopted for generating nuclear cross section for various temperatures in transport simulation. Among the existing methods

the SIGMA1 approach is exact but inefficient due to involving of error function and Taylor series expansion.

Purpose

In this paper

we proposed a piecewise Gauss quadrature method for on-the-fly Doppler broadening based on SuperMC to improve efficiency with given accuracy.

Methods

According to the cross section features of different energy regions

Gauss-Legendre quadrature was used in low-energy region

while the Gauss-Hermite quadrature used in high-energy region.

Results

The comparison of typical nuclides cross section and benchmarking with Godiva and Doppler coefficient of reactivity were presented in detail

which indicated that the new method could generate neutron cross section rapidly and precisely at various temperatures. Compared with SIGMA1 method

the proposed method improved the computing efficiency by an average of 5 times

and higher temperature could promote the broadening efficiency.

Conclusions

It showed the method could be applied in multi-physical coupling calculation of reactor.

关键词

Keywords

references

Trumbull T. Treatment of nuclear data for transport problems containing detailed temperature distribution[R]. Niskayuna, NY: Knolls Atomic Power Laboratory (KAPL), 2006.

G Yesilyurt , W Martin , F Brown . On-the-fly Doppler broadening for Monte Carlo codes . Nuclear Science and Engineering , 2012 . 171 ( 3 ): 239 - 257 . DOI: 10.13182/NSE11-67 http://doi.org/10.13182/NSE11-67 .

T Viitanen , J Leppanen . Explicit treatment of thermal motion in continuous-energy Monte Carlo tracking routines . Nuclear Science and Engineering , 2012 . 171 ( 2 ): 165 - 173 . DOI: 10.13182/NSE11-36 http://doi.org/10.13182/NSE11-36 .

B Forget , S Xu , K Smith . Direct Doppler broadening in Monte Carlo simulations using the multipole representation . Annals of Nuclear Energy , 2014 . 64 78 - 85 . DOI: 10.1016/j.anucene.2013.09.043 http://doi.org/10.1016/j.anucene.2013.09.043 .

D Cullen . Exact Doppler-broadening of tabulated cross section . Nuclear Science and Engineering , 1976 . 60 ( 3 ): 199 - 229 . DOI: 10.13182/NSE76-1 http://doi.org/10.13182/NSE76-1 .

Macfarlane R. The NJOY nuclear data processing system[R]. LA-UR-12-27079, Los Alamos National Laboratory, 2012.

Cullen D. PREPRO 2015-2015 ENDF/B pre-processing codes[R]. IAEA-NDS-39, International Atomic Energy Agency, 2015.

Dean C, Perry R, Neal R, et al . Validation of run-time Doppler broadening in MONK with JEFF3.1[C]. International Conference on Nuclear Data for Science and Technology, Jeju Island, South Korea, 2010.

P Romano , T Trumbull . Comparison of algorithm for Doppler broadening pointwise tabulated cross sections . Annals of Nuclear Energy , 2015 . 75 358 - 364 . DOI: 10.1016/j.anucene.2014.08.046 http://doi.org/10.1016/j.anucene.2014.08.046 .

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 .

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 ): 55 - 64 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201001009.htm .

Yican WU , Liqin HU , Yuetong LUO , . Development of design and analysis software for advanced nuclear systems . Chinese Journal of Nuclear Science and Engineering , 2010 . 30 ( 1 ): 55 - 64 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201001009.htm .

吴宜灿 , 宋婧 , 胡丽琴 , . 超级蒙特卡罗核计算仿真软件系统SuperMC . 核科学与工程 , 2016 . 36 ( 1 ): 62 - 71 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201601009.htm .

Yican WU , Jing SONG , Liqin HU , . Super Monte Carlo simulation program for nuclear and radiation process SuperMC . Chinese Journal of Nuclear Science and Engineering , 2016 . 36 ( 1 ): 62 - 71 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201601009.htm .

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

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 . DOI: 10.1088/0029-5515/47/11/015 http://doi.org/10.1088/0029-5515/47/11/015 .

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 1893 - 1903 . DOI: 10.1016/j.fusengdes.2007.08.012 http://doi.org/10.1016/j.fusengdes.2007.08.012 .

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

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 DOI: 10.1088/0029-5515/51/10/103036 http://doi.org/10.1088/0029-5515/51/10/103036 .

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

M H Wang , H Huang , C Lian , . Conceptual design of lead cooled reactor for hydrogen production . International Journal of Hydrogen Energy , 2015 . 40 15127 - 15131 . DOI: 10.1016/j.ijhydene.2015.04.009 http://doi.org/10.1016/j.ijhydene.2015.04.009 .

Q Y Huang , J Li , Y Chen . Study of irradiation effects in China low activation martensitic steel CLAM . Journal of Nuclear Materials , 2004 . 329-333 268 - 272 . DOI: 10.1016/j.jnucmat.2004.04.056 http://doi.org/10.1016/j.jnucmat.2004.04.056 .

Q Y Huang , S Gao , Z Q Zhu , . Progress in compatibility experiments on lithium-lead with candidate structural materials for fusion in China . Fusion Engineering and Design , 2009 . 84 242 - 246 . DOI: 10.1016/j.fusengdes.2008.12.038 http://doi.org/10.1016/j.fusengdes.2008.12.038 .

Briggs J, Michael A, Yolanda R. International handbook of evaluated criticality safety benchmark experiments[R]. NEA/NSC/DOC (95)03, Nuclear Energy Agency, 2006.

Mosteller R. ENDF/B-V, ENDF/B-VI, ENDF/B-Ⅶ.0 results for the Doppler-defect benchmark[R]. LA-UR-07-0922, Los Alamos National Laboratory, 2007.

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

On-the-fly nuclear cross section generation based on numerical integral method

Design and implementation of neutronics computing cloud platform based on SaaS mode

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

Multi-temperature cross section generation method in unresolved resonance energy region based on Neville interpolation

Monte Carlo critical boron concentration search method based on adjoint flux

Related Author

Rui CHEN

Shumin ZHOU

SONG Jing

WU Yican

LONG Pengcheng

HAO Lijuan

YU Shengpeng

WU Bin

Related Institution

Engineering Research Center for Nuclear Technology Application, Ministry of Education, East China University of Technology

Jiangxi Engineering Research Center of Process and Equipment for New Energy, East China University of Technology

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences

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

School of Mechanical and Electronic Engineering, East China University of Technology

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