Distribution of the effective dose of ionizing radiation in the central hall of the IGR reactor after startups

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
A. K. Mukhamediev, I. V. Prozorova, A. A. Prozorov
{"title":"Distribution of the effective dose of ionizing radiation in the central hall of the IGR reactor after startups","authors":"A. K. Mukhamediev,&nbsp;I. V. Prozorova,&nbsp;A. A. Prozorov","doi":"10.1007/s10512-025-01174-3","DOIUrl":null,"url":null,"abstract":"<div><p>The paper considers the developed calculation model of the IGR reactor with an upper cover and concrete biological protection. We have simulated photon transport using the MCNP5 code and the ENDF/B‑5, 6 constant libraries. IAEA and JAEA nuclear data libraries were used to describe the characteristics of fission products, as well as the processes of uranium-235 decay and gamma-ray field formation. The proposed approach can be used to spatially visualize the operating conditions of a nuclear reactor after startups. We have assessed the field and rate of the effective dose in the central hall of the IGR reactor during its operation at a constant power of 100 MW for 40 s. The effective dose rate was determined to estimate potential radiation load on small-sized neutron detectors (fission chambers). These detectors are supposed to measure local values of fast neutron flux density during irradiation of devices in the reactor. We have validated the proposed method for calculating the effective dose of gamma radiation using the results of direct measurements in the central reactor hall. Validation results confirm the correctness of the proposed calculation models and methods, as well as the admissibility of their use for assessing the radiation situation in the central hall of the IGR reactor.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"31 - 37"},"PeriodicalIF":0.4000,"publicationDate":"2025-03-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Atomic Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10512-025-01174-3","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The paper considers the developed calculation model of the IGR reactor with an upper cover and concrete biological protection. We have simulated photon transport using the MCNP5 code and the ENDF/B‑5, 6 constant libraries. IAEA and JAEA nuclear data libraries were used to describe the characteristics of fission products, as well as the processes of uranium-235 decay and gamma-ray field formation. The proposed approach can be used to spatially visualize the operating conditions of a nuclear reactor after startups. We have assessed the field and rate of the effective dose in the central hall of the IGR reactor during its operation at a constant power of 100 MW for 40 s. The effective dose rate was determined to estimate potential radiation load on small-sized neutron detectors (fission chambers). These detectors are supposed to measure local values of fast neutron flux density during irradiation of devices in the reactor. We have validated the proposed method for calculating the effective dose of gamma radiation using the results of direct measurements in the central reactor hall. Validation results confirm the correctness of the proposed calculation models and methods, as well as the admissibility of their use for assessing the radiation situation in the central hall of the IGR reactor.

IGR反应堆启动后中央大厅电离辐射有效剂量分布
本文考虑了已建立的具有上盖和混凝土生物防护的IGR反应器的计算模型。我们使用MCNP5代码和ENDF/B‑5,6常数库模拟了光子传输。利用原子能机构和日本原子能机构的核数据库描述了裂变产物的特征,以及铀-235衰变和伽马射线场形成的过程。该方法可用于对核反应堆启动后的运行状态进行空间可视化。我们评估了IGR反应堆在100 MW恒定功率下运行40 s时,中央大厅有效剂量的场和率。利用有效剂量率估算了小型中子探测器(裂变室)的潜在辐射负荷。这些探测器被用来测量反应堆中设备辐照时快中子通量密度的局部值。我们利用在中央反应堆大厅的直接测量结果验证了所提出的计算伽马辐射有效剂量的方法。验证结果证实了所提出的计算模型和方法的正确性,以及它们用于评估IGR反应堆中央大厅辐射状况的可接受性。
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 求助全文
来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
×
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
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
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 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信