基于内维尔插值的不可分辨共振能区多温度截面生成方法研究

陈锐; 周书民

doi:10.11889/j.0253-3219.2018.hjs.41.090601

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基于内维尔插值的不可分辨共振能区多温度截面生成方法研究

核能科学与工程 | 更新时间：2021-05-19

- 基于内维尔插值的不可分辨共振能区多温度截面生成方法研究
- Multi-temperature cross section generation method in unresolved resonance energy region based on Neville interpolation
- 核技术 2018年41卷第9期文章编号：090601
- 作者机构：
  
  1.东华理工大学江西省新能源工艺及装备工程技术研究中心南昌 330013
  2.东华理工大学机械与电子工程学院南昌 330013
- 作者简介：
  
  [ "陈锐, 男, 1981年出生, 2017年于中国科学技术大学获博士学位, 研究领域为核数据处理", "CHEN Rui, male, born in 1981, graduated from University of Science and Technology of China with a doctoral degree in 2017, focusing on nuclear data processing" ]
  周书民, E-mail:smzhou@ecit.edu.cn ZHOU Shumin, E-mail: smzhou@ecit.edu.cn
- 基金信息：
  
  国家自然科学基金(11565002);江西省教育厅计划项目(GJJ150558);江西省新能源工艺与装备工程技术研究中心开放基金(JXNE2017-04)
- DOI：10.11889/j.0253-3219.2018.hjs.41.090601
  中图分类号： TL329.2
- 收稿日期：2018-04-25，
  
  修回日期：2018-06-04，
  
  纸质出版日期：2018-09
- 稿件说明：
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陈锐, 周书民. 基于内维尔插值的不可分辨共振能区多温度截面生成方法研究[J]. 核技术, 2018,41(9):090601

Rui CHEN, Shumin ZHOU. Multi-temperature cross section generation method in unresolved resonance energy region based on Neville interpolation[J]. Nuclear techniques, 2018, 41(9): 090601
陈锐, 周书民. 基于内维尔插值的不可分辨共振能区多温度截面生成方法研究[J]. 核技术, 2018,41(9):090601 DOI： 10.11889/j.0253-3219.2018.hjs.41.090601.

Rui CHEN, Shumin ZHOU. Multi-temperature cross section generation method in unresolved resonance energy region based on Neville interpolation[J]. Nuclear techniques, 2018, 41(9): 090601 DOI： 10.11889/j.0253-3219.2018.hjs.41.090601.

摘要

对于具有快中子能谱的核能系统，其共振截面在不可分辨共振能区因受温度效应的影响，无法准确获得该能区内每个能量对应共振峰的截面，在计算不同温度截面时，需考虑采用与可分辨共振能区不同的计算方法。本文在充分调研国内外蒙特卡罗中子输运中的不可分辨共振能区在线核截面生成方法现状基础上，结合了各核素不同温度下概率表的特征，提出使用基于内维尔（Neville）插值的不可分辨共振能区多温度截面生成方法，在保证核截面精度的同时提高了截面生成效率。国际快堆堆芯模型Bigten1及Bigten2等测试结果表明：该方法与基准值的偏差小于10 pcm，证明了方法的准确性与有效性，可用于反应堆多物理耦合计算。

Abstract

Background

For a nuclear energy system with fast neutron spectrum

the cross section in unresolved resonance energy region is affected by the temperature effect and changes

hence

it is not possible to accurately obtain the section of each energy corresponding to the resonance peak in the energy region. When calculating the cross sections under various temperatures

the calculation method different from the resolved resonance energy region must be taken.

Purpose

This study aims to propose a novel multi-temperature cross section generation method to improve efficiency with given accuracy.

Methods

Based on the investigation of the status of the worldwide on-the-fly nuclear cross section generation methods for the unresolved resonance energy region in Monte Carlo neutron transport

the Neville interpolation is used for better efficiency according to the cross section features of probability table at different temperatures. This multi-temperature cross section generation method was verified on two publicly available reactor core models.

Results

Performance test results on international fast reactor core models

i.e.

Bigten1 and Bigten2

show that the deviation of the method and the reference value is less than 10 pcm

which proves the accuracy and effectiveness of the method.

Conclusion

The accuracy and effectiveness of this proposed method showed its applicability for reactor multi-physical coupling simulation.

关键词

Keywords

references

谢仲生 , 吴宏春 , 张少泓 . 核反应堆物理分析(修订本) , : 西安西安交通大学出版社 , 2004 . 22 - 23 .

Zhongsheng XIE , Hongchun WU , Shaohong ZHANG . Physical analysis of nuclear reactor (revised edition) , : Xi'an Xi'an Jiaotong University Press , 2004 . 22 - 23 .

R MacFarlane , A Kahler . Method for processing ENDF/BVⅡ with NJOY . Nuclear Data Sheets , 2011 . 111 2739 - 2890 . http://cn.bing.com/academic/profile?id=d872c27c57cce7123e4ebdca056ab063&encoded=0&v=paper_preview&mkt=zh-cn .

Macfarlane R, Muir D, Boicourt R, et al . The NJOY nuclear data processing system[R]. Version 2012. LA-UR-12-27079. Los Alamos National Laboratory, 2012.

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 .

Walsh J, Forget B, Smith K, et al . On-the-fly doppler broadening of unresolved resonance region cross sections[R]. LLNL-JRNL-704125-DRAFT. Lawrence Livermore National Laboratory, 2016.

Brown F. The makxsf code with doppler broadening[R]. LA-UR-06-7002. Los Alamos National Laboratory, 2006.

E Neville . Iterative interpolation . The Journal of the Indian Mathematical Society , 1933 . 20 87 - 120 . http://d.old.wanfangdata.com.cn/Periodical/gzxb200603036 .

W Press , S Teukolsky , W Vetterling , . Numerical recipes , 3rd ed : New York Cambridge University Press , 2007 . 118 - 124 .

NEA Data Bank. JEFF-3.2 evaluated data library-Neutron data[EB/OL]. 2016. http://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/ http://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/ .

Frankle S. A suite of criticality benchmarks for validating nuclear data[R]. LA-13594. Los Alamos National Laboratory, 1999.

A Kahler , R MacFarlane , R Mosteller , . ENDF/B-VⅡ.1 Neutron cross section data testing with critical assembly benchmarks and reactor experiments . Nuclear Data Sheets , 2011 . 112 ( 12 ): 2997 - 3036 . DOI: 10.1016/j.nds.2011.11.003 http://doi.org/10.1016/j.nds.2011.11.003 .

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