Yucheng Zhou , Xiaoming Chen , Yijian Zhan , Zhiyao Xue , Jifeng Hu , Xiaohe Wang , Mintao Zhu , Deliang Li
{"title":"蛇纹石混凝土(SC)的热中子屏蔽效应研究","authors":"Yucheng Zhou , Xiaoming Chen , Yijian Zhan , Zhiyao Xue , Jifeng Hu , Xiaohe Wang , Mintao Zhu , Deliang Li","doi":"10.1016/j.radphyschem.2025.112535","DOIUrl":null,"url":null,"abstract":"<div><div>Fourth-generation advanced reactor systems have extremely high safety and antinuclear radiation diffusion requirements. The material design of nuclear radiation shielding concrete in reactor construction is important. In this work, the thermal neutron shielding performance of serpentine concrete (SC) is examined for a thermal neutron reactor—the molten salt reactor project. The effects of thermal neutrons in different energy segments on the SC shielding are investigated using a photoneutron source (PNS) driven by a 15 MeV electron linear accelerator (LINAC) and Monte Carlo (MCNP) simulations. The results show that the difference between SC and normal concrete (NC) lies in its higher content of H, Fe and Mg; among these elements, the comprehensive cross sections of H and Fe are greater than those of the other main elements, and the thermal neutron shielding effect of SC is approximately 25% greater than that of NC. Due to the thermal neutron scattering (TNS) effect, the <0.01 eV thermal neutron transmission of concrete significantly increases, and the thermal neutron transmission difference of the low thickness concrete is significant and needs to be considered in engineering construction. This study provides support for the engineering construction of advanced reactors and is highly important for reducing the spread of nuclear radiation.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112535"},"PeriodicalIF":2.8000,"publicationDate":"2025-01-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Research on thermal neutron shielding effect of serpentine concrete (SC)\",\"authors\":\"Yucheng Zhou , Xiaoming Chen , Yijian Zhan , Zhiyao Xue , Jifeng Hu , Xiaohe Wang , Mintao Zhu , Deliang Li\",\"doi\":\"10.1016/j.radphyschem.2025.112535\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Fourth-generation advanced reactor systems have extremely high safety and antinuclear radiation diffusion requirements. The material design of nuclear radiation shielding concrete in reactor construction is important. In this work, the thermal neutron shielding performance of serpentine concrete (SC) is examined for a thermal neutron reactor—the molten salt reactor project. The effects of thermal neutrons in different energy segments on the SC shielding are investigated using a photoneutron source (PNS) driven by a 15 MeV electron linear accelerator (LINAC) and Monte Carlo (MCNP) simulations. The results show that the difference between SC and normal concrete (NC) lies in its higher content of H, Fe and Mg; among these elements, the comprehensive cross sections of H and Fe are greater than those of the other main elements, and the thermal neutron shielding effect of SC is approximately 25% greater than that of NC. Due to the thermal neutron scattering (TNS) effect, the <0.01 eV thermal neutron transmission of concrete significantly increases, and the thermal neutron transmission difference of the low thickness concrete is significant and needs to be considered in engineering construction. This study provides support for the engineering construction of advanced reactors and is highly important for reducing the spread of nuclear radiation.</div></div>\",\"PeriodicalId\":20861,\"journal\":{\"name\":\"Radiation Physics and Chemistry\",\"volume\":\"229 \",\"pages\":\"Article 112535\"},\"PeriodicalIF\":2.8000,\"publicationDate\":\"2025-01-17\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Radiation Physics and Chemistry\",\"FirstCategoryId\":\"92\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0969806X25000271\",\"RegionNum\":3,\"RegionCategory\":\"物理与天体物理\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"CHEMISTRY, PHYSICAL\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Radiation Physics and Chemistry","FirstCategoryId":"92","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0969806X25000271","RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"CHEMISTRY, PHYSICAL","Score":null,"Total":0}
Research on thermal neutron shielding effect of serpentine concrete (SC)
Fourth-generation advanced reactor systems have extremely high safety and antinuclear radiation diffusion requirements. The material design of nuclear radiation shielding concrete in reactor construction is important. In this work, the thermal neutron shielding performance of serpentine concrete (SC) is examined for a thermal neutron reactor—the molten salt reactor project. The effects of thermal neutrons in different energy segments on the SC shielding are investigated using a photoneutron source (PNS) driven by a 15 MeV electron linear accelerator (LINAC) and Monte Carlo (MCNP) simulations. The results show that the difference between SC and normal concrete (NC) lies in its higher content of H, Fe and Mg; among these elements, the comprehensive cross sections of H and Fe are greater than those of the other main elements, and the thermal neutron shielding effect of SC is approximately 25% greater than that of NC. Due to the thermal neutron scattering (TNS) effect, the <0.01 eV thermal neutron transmission of concrete significantly increases, and the thermal neutron transmission difference of the low thickness concrete is significant and needs to be considered in engineering construction. This study provides support for the engineering construction of advanced reactors and is highly important for reducing the spread of nuclear radiation.
期刊介绍:
Radiation Physics and Chemistry is a multidisciplinary journal that provides a medium for publication of substantial and original papers, reviews, and short communications which focus on research and developments involving ionizing radiation in radiation physics, radiation chemistry and radiation processing.
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. This could include papers that are very similar to previous publications, only with changed target substrates, employed materials, analyzed sites and experimental methods, report results without presenting new insights and/or hypothesis testing, or do not focus on the radiation effects.