Please use this identifier to cite or link to this item: http://bura.brunel.ac.uk/handle/2438/28941
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dc.contributor.authorYang, L-Q-
dc.contributor.authorLiu, Y-K-
dc.contributor.authorPeng, M-J-
dc.contributor.authorAyodeji, A-
dc.contributor.authorChen, Z-T-
dc.contributor.authorLong, Z-Y-
dc.date.accessioned2024-05-07T09:07:56Z-
dc.date.available2024-05-07T09:07:56Z-
dc.date.issued2021-07-15-
dc.identifierORCiD: Yong-kuo Liu https://orcid.org/0000-0001-7729-7154-
dc.identifierORCiD: Abiodun Ayodeji https://orcid.org/0000-0003-3257-7616-
dc.identifier.citationYang, L.-Q. et al (2022) 'Radioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioning', Nuclear Engineering and Technology, 54 (1), pp. 293 - 300. doi: 10.1016/j.net.2021.07.017.en_US
dc.identifier.issn1738-5733-
dc.identifier.urihttps://bura.brunel.ac.uk/handle/2438/28941-
dc.description.abstractDuring the decommissioning of the nuclear facilities, the radioactive gases in pressure vessels may leak due to the demolition operations. The decommissioning site has large space, slow air circulation, and many large nuclear facilities, which increase the difficulty of workers' inhalation exposure assessment. In order to dynamically evaluate the activity distribution of radionuclides and the committed effective dose from inhalation in nuclear decommissioning environment, an inhalation exposure assessment method based on the modified eddy-diffusion model and the inhaled dose conversion factor is proposed in this paper. The method takes into account the influence of building, facilities, exhaust ducts, etc. on the distribution of radioactive gases, and can evaluate the influence of radioactive gases diffusion on workers during the decommissioning of nuclear facilities.en_US
dc.description.sponsorshipFundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Decommissioning of Nuclear Facilities and Radioactive Waste Management Research, Project supported by the Natural Science Foundation of Heilongjiang Province, China (Grant NO. A2016002); technical support project for Suzhou Nuclear Power Research Institute(SNPI) (NO.029-GN-B-2018-C45-P.0.99–00003); Foundation of Science and Technology on Reactor System Design Technology Laboratory (HT-KFKT-14-2017003); project of Research Institute of Nuclear Power Operation (No.RIN180149-SCCG).en_US
dc.format.extent293 - 300-
dc.format.extentPrint-Electronic-
dc.languageEnglish-
dc.language.isoen_USen_US
dc.publisherElsevier on behalf of the Korean Nuclear Societyen_US
dc.rightsCopyright © 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/).-
dc.rights.urihttps://creativecommons.org/licenses/by-nc-nd/4.0/-
dc.subjectradioactive gasen_US
dc.subjectair modelingen_US
dc.subjecteddy-diffusion modelen_US
dc.subjectexposure assessmenten_US
dc.subjectnuclear decommissioningen_US
dc.titleRadioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioningen_US
dc.typeArticleen_US
dc.date.dateAccepted2021-07-13-
dc.identifier.doihttps://doi.org/10.1016/j.net.2021.07.017-
dc.relation.isPartOfNuclear Engineering and Technology-
pubs.issue1-
pubs.publication-statusPublished-
pubs.volume54-
dc.identifier.eissn2234-358X-
dc.rights.licensehttps://creativecommons.org/licenses/by-nc-nd/4.0/legalcode.en-
dc.rights.holderKorean Nuclear Society-
Appears in Collections:Brunel Innovation Centre

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