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dc.contributor.authorHristova, Rayna
dc.contributor.authorSimovski, Stefan
dc.date.accessioned2024-12-24T19:15:45Z
dc.date.available2024-12-24T19:15:45Z
dc.date.copyright6/17/2024 12:00:00 AM
dc.date.issued2024
dc.identifier.issn2332-8983
dc.identifier.otherners_010_04_040802.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303608
dc.description.abstractIn the complex situation in which we live, preventive measures are increasingly being taken against the threat of nuclear attack and ionizing radiation, nuclear shelters are being built for private and public purposes. The purpose of the authors is to provide a practical approach to quickly calculate the thickness of the concrete shelter wall for such cases. The shelter wall thickness is assessed on the basis of published data on radiation dose calculations, corroborated by field data from nuclear tests, and information or calculations of the dose attenuation in the shelter wall. Doses from nuclear tests or simulations are summarized in tables in relation to bomb yield and distance from the explosion point. A dose criterion is chosen as the acceptable dose behind the shield. Neutron dose transmission factors, defined as ratio of the dose criterion to the dose without shielding are calculated. The concrete wall thickness corresponding to the neutron dose transmission factor was taken from reference sources. For gamma rays, the shield thickness is calculated based on an analytical relationship between dose without shield, the dose criterion, and the shield thickness. Data tables are provided with the estimated concrete wall thickness in relation to bomb yield and distance.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titlePractical Approach to Nuclear Shelter Wall Thickness Estimation
dc.typeJournal Paper
dc.journal.volume10
dc.journal.issue4
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4065463
dc.journal.fristpage40802-1
dc.journal.lastpage40802-8
dc.page8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 004
dc.contenttypeFulltext


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