ON MODELLING OF THE INITIAL SOURCE OF PROMPT NEUTRONS FOR SOLV-ING NONSTATIONARY PROBLEMS BY THE MONTE CARLO METHOD

M. Ioannisian, V. Davidenko, I. Dyachkov
{"title":"ON MODELLING OF THE INITIAL SOURCE OF PROMPT NEUTRONS FOR SOLV-ING NONSTATIONARY PROBLEMS BY THE MONTE CARLO METHOD","authors":"M. Ioannisian, V. Davidenko, I. Dyachkov","doi":"10.55176/2414-1038-2020-3-88-96","DOIUrl":null,"url":null,"abstract":"The work is devoted to the problem of initial neutron source distribution for modeling kinetic transient processes by the direct analogue Monte Carlo method. An algorithm is proposed for modeling such a source. The source algorithm implemented in the KIR2 program and designed to solve the problem of taking the system out of the critical state by introducing a perturbation (reactivity). Only prompt neutrons are considered. For the neutron source distribution, a phase coordinates of the neutron are used. The phase coordinates are determined in the preliminary calculation of the critical state. The results of testing the algorithm on non-stationary test problems (an infinite environment and RP1GS) are presented. In each task, the geometric area is filled with material presented in the form of single-group macroparameters. The results of calculating the integral neutron flux density were compared with the solution of the point kinetics equations. Good agreement was obtained - the deviation during all the calculated processes does not exceed 0.4 % in the integrated flux density, but it increases at the end of the processes with the introduction of negative reactivity up to 2.5 % with a small number of neutrons in the system.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2020-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.55176/2414-1038-2020-3-88-96","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

The work is devoted to the problem of initial neutron source distribution for modeling kinetic transient processes by the direct analogue Monte Carlo method. An algorithm is proposed for modeling such a source. The source algorithm implemented in the KIR2 program and designed to solve the problem of taking the system out of the critical state by introducing a perturbation (reactivity). Only prompt neutrons are considered. For the neutron source distribution, a phase coordinates of the neutron are used. The phase coordinates are determined in the preliminary calculation of the critical state. The results of testing the algorithm on non-stationary test problems (an infinite environment and RP1GS) are presented. In each task, the geometric area is filled with material presented in the form of single-group macroparameters. The results of calculating the integral neutron flux density were compared with the solution of the point kinetics equations. Good agreement was obtained - the deviation during all the calculated processes does not exceed 0.4 % in the integrated flux density, but it increases at the end of the processes with the introduction of negative reactivity up to 2.5 % with a small number of neutrons in the system.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
用蒙特卡罗方法求解非平稳问题时提示中子初始源的建模
研究了用直接模拟蒙特卡罗方法模拟动力学瞬态过程的初始中子源分布问题。提出了一种对这种源进行建模的算法。源算法在KIR2程序中实现,旨在解决通过引入扰动(反应性)使系统脱离临界状态的问题。只考虑瞬发中子。对于中子源的分布,采用了中子的相坐标。在临界状态的初步计算中确定了相坐标。给出了算法在非平稳测试问题(无限环境和RP1GS)上的测试结果。在每个任务中,几何区域被以单组宏参数形式呈现的材料填充。将积分中子通量密度的计算结果与点动力学方程的解进行了比较。得到了很好的一致性——在所有计算过程中,总通量密度的偏差不超过0.4%,但在过程结束时,随着系统中少量中子的负反应性的引入,偏差增加到2.5%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 去求助
来源期刊
自引率
0.00%
发文量
0
期刊最新文献
POSSIBILITY OF APPLICATION OF ZrO2-MgO-CaO CRUCIBLES FOR PRODUCING ALLOY U-10 % Zr CALCULATION ESTIMATION OF THE REQUIRED HEAT GENERATION IN TESTING FUEL ELEMENTS TO ACHIEVE SUPERCRITICAL PARAMETERS OF THE COOLANT UNDER IRRADIATION IN THE RESEARCH NUCLEAR REACTOR FEATURES OF THERMAL HYDRAULICS OF ACTIVE ZONES OF FAST LOW-POWER AND HIGH-POWER SODIUM PRODUCTION REACTORS FOR A CLOSED FUEL CYCLE SYSTEM CALCULATION OF THE STRUCTURAL MATERIALS ACTIVATION BY A FUSION NEUTRON FLUX WITH BPSD CODE HEAT PIPES IN NUCLEAR ENGINEERING
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1