CEFR首炉堆芯核设计计算不确定度分析

张坚; 喻宏; 胡赟; 徐李

doi:10.7538/yzk.2018.youxian.0275

CEFR首炉堆芯核设计计算不确定度分析

中国原子能科学研究院反应堆工程技术研究部,北京102413

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- 刊出日期: 2019-02-19

Uncertainty Analysis on Nuclear Design Calculation of the First Loading Core of CEFR

China Institute of Atomic Energy, P. O. Box 275-95, Beijing 102413, China

摘要

摘要: 在中国实验快堆（CEFR）设计阶段，堆芯计算不确定度分析主要是基于在俄罗斯开展的零功率模拟实验获得的，相关不确定度的理论分析评价工作存在不足。本文采用统计抽样方法、确定论微扰方法及直接扰动方法，通过对不确定度来源进行计算分析，给出了堆芯核设计计算的主要结果参数，包括k_eff、控制棒价值、钠空泡效应及功率分布的不确定度定量评价。通过CEFR的分析工作，建立了核设计不确定度评价的方法流程，为后续中国示范快堆核设计的不确定度评价分析奠定了基础。
- 中国实验快堆 ,
- 核设计 ,
- 不确定度分析
Abstract: In the design phase of China Experimental Fast Reactor (CEFR), the uncertainty analysis was mainly based on the zero-power simulation experiment in Russia. There are some shortages in the work of nuclear design uncertainty analysis and evaluation. In this paper, based on statistical sampling method, deterministic theory perturbation method and direct perturbation method, different sources of uncertainty were evaluated. The uncertainty of main nuclear calculation results such as k_eff, control rod worth, sodium void effect and power distribution was given. Through the analysis work of CEFR, a method framework for the evaluation of uncertainty was established. The framework and method lay the foundation for the uncertainty analysis of nuclear design for China Demonstration Fast Reactor.
- China Experimental Fast Reactor ,
- nuclear design ,
- uncertainty analysis

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CEFR首炉堆芯核设计计算不确定度分析

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出版历程

Uncertainty Analysis on Nuclear Design Calculation of the First Loading Core of CEFR

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出版历程

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