基于分段高斯积分的在线多温度核截面生成方法研究

陈锐; 郝丽娟; 宋婧; 吴斌; 何鹏

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

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基于分段高斯积分的在线多温度核截面生成方法研究

核物理、交叉学科研究 | 更新时间：2021-05-19

- 基于分段高斯积分的在线多温度核截面生成方法研究
- On-the-fly Doppler broadening method based on piecewise Gauss quadrature for generating neutron cross section
- 核技术 2017年40卷第4期文章编号：040503
- 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：
  
  [ "陈锐, 男, 1981年出生, 2009年毕业于东华理工大学, 现为博士研究生, 研究领域为核数据处理", "CHEN Rui, male, born in 1981, graduated from East China Institute of Technology in 2009, doctoral student, focusing on nuclear data processing" ]
  何鹏, E-mail:peng.he@fds.org.cn HE Peng, E-mail:peng.he@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)
- DOI：10.11889/j.0253-3219.2017.hjs.40.040503
  中图分类号： TL329.2
- 收稿日期：2016-12-08，
  
  修回日期：2016-12-26，
  
  纸质出版日期：2017-04-10
- 稿件说明：
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陈锐, 郝丽娟, 宋婧, 等. 基于分段高斯积分的在线多温度核截面生成方法研究[J]. 核技术, 2017,40(4):040503

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
陈锐, 郝丽娟, 宋婧, 等. 基于分段高斯积分的在线多温度核截面生成方法研究[J]. 核技术, 2017,40(4):040503 DOI： 10.11889/j.0253-3219.2017.hjs.40.040503.

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.

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