{"title":"Efficacy of advanced concretes for attenuation of ionizing radiations: A comprehensive review and comparison","authors":"Rajni Devi , Poonamjot , Mohinder Singh , Amandeep Sharma","doi":"10.1016/j.pnucene.2024.105502","DOIUrl":null,"url":null,"abstract":"<div><div>Radiation shielding materials are key components to suppress the hazardous effects of ionizing radiation, especially energetic gamma rays and penetrative neutrons. This review includes the most ancient building material, concrete, in its different composition obtained by introducing a variety of additives, aggregates and nanomaterials in its conventional form. The objective of present work is to critically review and compare the variety of concretes, reported through various experimental and computational methods, so that the best composition among diverse concrete categories can be highlighted. For this purpose the essential shielding parameters namely mass attenuation coefficient (MAC) and half value layer (HVL) at useful gamma energies of 662, 1173 and 1332 keV have been compared graphically. The protective shielding concretes against neutrons have also been studied through a plot corresponding to Fast Neutron Removal Cross-sections (FNRCS) data of different concretes. Lastly, shielding competency of granite and pyroclastic rock samples for light and heavy charged particles have been included by taking into consideration the interaction parameters namely mass stopping power and projected range. Apart from this, numerous advanced applications of radiation shielding concretes, proper utilization of different forms of waste in concrete mix and few shortcomings of concrete specimens are also listed in this review paper. From the comparative plots of various concretes it is concluded that marble based concretes are best for gamma ray attenuation and nanomaterials based compositions are top if lesser thickness is to employ for attenuation. On the basis of acquired knowledge from literature, the present work will highlight the future perspectives of concretes as shielding materials and would be quite helpful for the selection of appropriate compositions by the community interacting directly or indirectly with ionizing radiations.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"178 ","pages":"Article 105502"},"PeriodicalIF":3.3000,"publicationDate":"2024-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197024004529","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Radiation shielding materials are key components to suppress the hazardous effects of ionizing radiation, especially energetic gamma rays and penetrative neutrons. This review includes the most ancient building material, concrete, in its different composition obtained by introducing a variety of additives, aggregates and nanomaterials in its conventional form. The objective of present work is to critically review and compare the variety of concretes, reported through various experimental and computational methods, so that the best composition among diverse concrete categories can be highlighted. For this purpose the essential shielding parameters namely mass attenuation coefficient (MAC) and half value layer (HVL) at useful gamma energies of 662, 1173 and 1332 keV have been compared graphically. The protective shielding concretes against neutrons have also been studied through a plot corresponding to Fast Neutron Removal Cross-sections (FNRCS) data of different concretes. Lastly, shielding competency of granite and pyroclastic rock samples for light and heavy charged particles have been included by taking into consideration the interaction parameters namely mass stopping power and projected range. Apart from this, numerous advanced applications of radiation shielding concretes, proper utilization of different forms of waste in concrete mix and few shortcomings of concrete specimens are also listed in this review paper. From the comparative plots of various concretes it is concluded that marble based concretes are best for gamma ray attenuation and nanomaterials based compositions are top if lesser thickness is to employ for attenuation. On the basis of acquired knowledge from literature, the present work will highlight the future perspectives of concretes as shielding materials and would be quite helpful for the selection of appropriate compositions by the community interacting directly or indirectly with ionizing radiations.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.