Design and modeling of Cf-252 -based neutron irradiator for NAA: MCNP6 simulations of dose rate and neutron fluxes

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes Pub Date : 2025-06-10 DOI:10.1016/j.apradiso.2025.111990

L.B. Fontana , J. Yu , M.P. Short , T. Durak , E. Lamere , M.S. Galanek , A. Safarov , H.M. Wainwright

{"title":"Design and modeling of Cf-252 -based neutron irradiator for NAA: MCNP6 simulations of dose rate and neutron fluxes","authors":"L.B. Fontana , J. Yu , M.P. Short , T. Durak , E. Lamere , M.S. Galanek , A. Safarov , H.M. Wainwright","doi":"10.1016/j.apradiso.2025.111990","DOIUrl":null,"url":null,"abstract":"<div><div>This paper presents a new design and modeling of a rapid, multiple sample Cf-252 irradiator for neutron activation analysis (NAA) to replace research reactor irradiations, with a particular focus on safety analysis associated with neutron and gamma dose rates in areas typically occupied by individuals. The study utilizes the Monte Carlo N-Particle (MCNP6) simulation code to assess three different configurations aimed at optimizing safety and operational efficiency. A<sup>252</sup>Cf source emitting 5.77 × 10<sup>7</sup> neutrons per second is considered. Simulations were conducted to determine optimal shielding configurations that comply with established radiation exposure limits. Ricorad™, a borated polyethylene material known for its exceptional neutron shielding performance due to its high hydrogen concentration, was specifically utilized for efficient and lightweight shielding. Additionally, the study examines the distribution of neutron flux around the <sup>252</sup>Cf source to ensure optimal sample placement for <sup>75</sup>As activation – a key output of planned activation studies. Furthermore, the paper examines practical irradiation applications at this sample position by estimating the measurement time needed to achieve 2000 counts for the <sup>76</sup>As peak at 559.101 keV in a sample of coal fly ash using a high-purity germanium detector. The overarching goal of this work is to ensure safe and efficient utilization of a<sup>252</sup>Cf-based neutron irradiator for NAA, emphasizing the importance of radiation safety while minimizing space requirements and enabling accurate and reliable measurements.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111990"},"PeriodicalIF":1.6000,"publicationDate":"2025-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Applied Radiation and Isotopes","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0969804325003355","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"CHEMISTRY, INORGANIC & NUCLEAR","Score":null,"Total":0}

引用次数: 0

Abstract

This paper presents a new design and modeling of a rapid, multiple sample Cf-252 irradiator for neutron activation analysis (NAA) to replace research reactor irradiations, with a particular focus on safety analysis associated with neutron and gamma dose rates in areas typically occupied by individuals. The study utilizes the Monte Carlo N-Particle (MCNP6) simulation code to assess three different configurations aimed at optimizing safety and operational efficiency. A²⁵²Cf source emitting 5.77 × 10⁷ neutrons per second is considered. Simulations were conducted to determine optimal shielding configurations that comply with established radiation exposure limits. Ricorad™, a borated polyethylene material known for its exceptional neutron shielding performance due to its high hydrogen concentration, was specifically utilized for efficient and lightweight shielding. Additionally, the study examines the distribution of neutron flux around the ²⁵²Cf source to ensure optimal sample placement for ⁷⁵As activation – a key output of planned activation studies. Furthermore, the paper examines practical irradiation applications at this sample position by estimating the measurement time needed to achieve 2000 counts for the ⁷⁶As peak at 559.101 keV in a sample of coal fly ash using a high-purity germanium detector. The overarching goal of this work is to ensure safe and efficient utilization of a²⁵²Cf-based neutron irradiator for NAA, emphasizing the importance of radiation safety while minimizing space requirements and enabling accurate and reliable measurements.

查看原文本刊更多论文

基于Cf-252的中子辐照体设计与建模，用于NAA: MCNP6剂量率和中子通量模拟

本文介绍了一种用于中子活化分析（NAA）的快速、多样品Cf-252辐照器的新设计和建模，以取代研究堆辐照，特别关注与中子和伽马剂量率相关的安全性分析。该研究利用蒙特卡罗n -粒子（MCNP6）模拟代码来评估三种不同的配置，旨在优化安全性和操作效率。考虑了每秒发射5.77 × 107中子的A252Cf源。进行模拟以确定符合既定辐射暴露限值的最佳屏蔽配置。Ricorad™是一种硼化聚乙烯材料，因其高氢浓度而具有卓越的中子屏蔽性能，专门用于高效轻质屏蔽。此外，该研究还检查了252Cf源周围的中子通量分布，以确保75As活化的最佳样品放置-计划活化研究的关键输出。此外，本文通过估算使用高纯度锗探测器对煤飞灰样品中559.101 keV的76As峰进行2000次计数所需的测量时间，考察了该样品位置的实际辐照应用。这项工作的总体目标是确保安全有效地利用基于a252cf的中子辐照器用于NAA，强调辐射安全的重要性，同时最小化空间要求并实现准确可靠的测量。

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

Applied Radiation and Isotopes 工程技术-核科学技术

CiteScore

3.00

自引率

12.50%

发文量

406

审稿时长

13.5 months

期刊介绍： Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.