{"title":"Shielding design and heat transfer analysis of the transportation container of a hot batch in the 99Mo production facility","authors":"Abouzar Kiyani , Ali Bahrami Samani , Reza Pourimani , Seyed Milad Miremad","doi":"10.1016/j.apradiso.2025.111672","DOIUrl":null,"url":null,"abstract":"<div><div>In molybdenum-99 (<sup>99</sup>Mo) production facilities via the fission method, appropriate transportation containers must be used to transfer irradiated targets from the irradiation facility to the processing facility, following the requirements for transferring radioactive materials. In the <sup>99</sup>Mo production industrial plan of Iran, the transportation container must be capable of carrying a holster containing nine irradiated low-enriched uranium targets, known as a hot batch. In this article, the proper shielding of two-layer containers based on the gamma spectrum emitted from the radioisotope inventory of a local hot batch, including fission products, activation products, and other radioisotopes produced from their decay chains, was investigated by using Monte Carlo code MCNP6. The simulation results indicated that a two-part container including a moving part of depleted uranium with a thickness of 7 cm and a fixed part of lead with a thickness of 7.2 cm could be an appropriate choice for the local hot batch transport. Also, heat transfer analysis using ANSYS software showed that transporting the hot batch immersed in water inside the container improved thermal distribution.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111672"},"PeriodicalIF":1.6000,"publicationDate":"2025-01-13","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/S096980432500017X","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
In molybdenum-99 (99Mo) production facilities via the fission method, appropriate transportation containers must be used to transfer irradiated targets from the irradiation facility to the processing facility, following the requirements for transferring radioactive materials. In the 99Mo production industrial plan of Iran, the transportation container must be capable of carrying a holster containing nine irradiated low-enriched uranium targets, known as a hot batch. In this article, the proper shielding of two-layer containers based on the gamma spectrum emitted from the radioisotope inventory of a local hot batch, including fission products, activation products, and other radioisotopes produced from their decay chains, was investigated by using Monte Carlo code MCNP6. The simulation results indicated that a two-part container including a moving part of depleted uranium with a thickness of 7 cm and a fixed part of lead with a thickness of 7.2 cm could be an appropriate choice for the local hot batch transport. Also, heat transfer analysis using ANSYS software showed that transporting the hot batch immersed in water inside the container improved thermal distribution.
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.