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

Rui CHEN; Shumin ZHOU

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

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

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Multi-temperature cross section generation method in unresolved resonance energy region based on Neville interpolation
- NUCLEAR TECHNIQUES Vol. 41, Issue 9, Article number: 090601(2018)
- 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：
- 基金信息：
  
  National Natural Science Foundation of China;Jiangxi Provincial Education Department Project;Open Project Program of Jiangxi Engineering Research Center of Process and Equipment for New Energy
- DOI：10.11889/j.0253-3219.2018.hjs.41.090601
  CLC： TL329.2
- Received：25 April 2018，
  
  Revised：04 June 2018，
  
  Published：2018-09
- 稿件说明：
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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：

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

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