Study on Assessment of Nuclear Data and Neutronics Calculations through Critical Experiments

通过关键实验评估核数据和中子学计算的研究

基本信息

批准号：
02452294
负责人：
SHIROYA Seiji
金额：
$ 3.97万
依托单位：
KYOTO UNIVERSITY
依托单位国家：
日本
项目类别：
Grant-in-Aid for General Scientific Research (B)
财政年份：
1990
资助国家：
日本
起止时间：
1990 至 1992
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/en/grant/KAKENHI-PROJECT-02452294/
关键词：
Nuclear Data Neutronics Calculation Critical Experiment Tight-Pitch Lattice Core Moderator-to-Fuel Volume Ratio Self-Shielding Effect Effective Cross Section KUCA 核計算コード中性子スペクトル ENDF B-IV JENDL-3 減速材対燃料体積化燃料板バンチングウラン核デ-タ /

项目摘要

A study on the assessment of the nuclear data and neutronics calculations was performed through the critical experiments on the tight-pitch lattice cores loaded with uranium fuel and moderated by polyethylene.In this series of critical experiments using the Kyoto University Critical Assembly (KUCA), the moderator-to fuel volume ratio (V_m/V_f ratio) and the average enrichment of ^<235>U in the core were systematically varied to obtain the benchmark data for the assessment of the nuclear data and neutronics calculations. Monte Carlo calculations were executed to assess the validity of the nuclear data and the computational methods used in the neutronics calculation.Through the present study, it was found that the use of the current version of evaluated nuclear data file in Japan, JENDL-3, tends to underestimate the effective multiplication factor in comparison with the measured one and the cal-culated result by ENDF/B-IV which is a previous version of evaluated nuclear data file in the United States, whereas the use of a previous version in Japan, JENDL-2, tends to overestimate the effective multiplication factor. For the generation process of effective cross sections, it was found that one should properly take into account the interference effect in resonance self-shielding of uranium contained in two adjacent regions. It was also found that the trans-port effect can not be neglected in the diffusion calculation and the result com-parable to the accurate transport calculation can be obtained on the basis of the diffusion calculation by correcting the transport,energy group and mesh effects.

通过对带有铀燃料并通过聚乙烯进行调节的紧密实验进行的关键实验进行了有关核数据和中子计算的评估的研究。在这一系列的关键实验中，使用京都大学关键组装（KUCA）（KUCA）（KUCA），主持人到燃料量的比例（v_m/v_f比例）<<<v_m/v_f比例的平均值<<<135为了获得基准数据以评估核数据和中子学计算。执行了蒙特卡洛计算以评估核数据的有效性和中性计算中使用的计算方法。通过本研究，发现日本评估核数据的当前版本的使用，Jendl-3，Jendl-3，倾向于低估与核数据相比，与核心数据相比，与以前的核定数据相比，与以前的核能相比，与以前的b--相比，该文件是一个版本，该版本是一个版本，即核定的car-iv/b-iv，该版本是一个版本，该版本是一个版本，该版本是一个版本，该版本是一个版本，该版本是一个版本。日本以前版本的Jendl-2倾向于高估有效的乘法因子。对于有效的横截面的生成过程，发现应该正确考虑在两个相邻区域中包含的铀的共振自屏蔽中的干扰效应。还发现，在扩散计算中不能忽略跨端口效应，并且可以通过纠正传输，能量组和网格效应来基于扩散计算获得与准确的运输计算相吻合的结果。