Пожалуйста, используйте этот идентификатор, чтобы цитировать или ссылаться на этот ресурс: http://elar.urfu.ru/handle/10995/118339
Полная запись метаданных
Поле DCЗначениеЯзык
dc.contributor.authorTashlykov, O. L.en
dc.contributor.authorAlqahtani, M. S.en
dc.contributor.authorMahmoud, K. A.en
dc.date.accessioned2022-10-19T05:25:14Z-
dc.date.available2022-10-19T05:25:14Z-
dc.date.issued2022-
dc.identifier.citationTashlykov O. L. The role of natural rock filler in optimizing the radiation protection capacity of the intermediate-level radioactive waste containers / O. L. Tashlykov, M. S. Alqahtani, K. A. Mahmoud // Nuclear Engineering and Technology. — 2022. — Vol. 54. — Iss. 10. — P. 3849-3854.en
dc.identifier.issn17385733-
dc.identifier.otherhttps://www.scopus.com/inward/record.uri?eid=2-s2.0-85131418190&doi=10.1016%2fj.net.2022.05.014&partnerID=40&md5=5e755d2bb9045651902f682eb46095felink
dc.identifier.urihttp://elar.urfu.ru/handle/10995/118339-
dc.description.abstractThe present work aims to optimize the radiation protection efficiency for ion-selective containers used in the liquid treatment for the nuclear power plant (NPP) cooling cycle. Some naturally occurring rocks were examined as filler materials to reduce absorbed dose and equivalent dos received from the radioactive waste container. Thus, the absorbed dose and equivalent dose were simulated at a distance of 1 m from the surface of the radioactive waste container using the Monte Carlo simulation. Both absorbed dose and equivalent dose rate are reduced by raising the filler thickness. The total absorbed dose is reduced from 7.66E-20 to 1.03E-20 Gy, and the equivalent dose is rate reduced from 183.81 to 24.63 μSv/h, raising the filler thickness between 0 and 17 cm, respectively. Also, the filler type significantly affects the equivalent dose rate, where the redorded equivalent dose rates are 24.63, 24.08, 27.63, 33.80, and 36.08 μSv/h for natural rocks basalt-1, basalt-2, basalt-sill, limestone, and rhyolite, respectively. The mentioned results show that the natural rocks, especially a thicker thickness (i.e., 17 cm thickness) of natural rocks basalt-1 and basalt-2, significantly reduce the gamma emissions from the radioactive wastes inside the modified container. Moreover, using an outer cementation concrete wall of 15 cm causes an additional decrease in the equivalent dose rate received from the container where the equivalent dose rate dropped to 6.63 μSv/h. © 2022 Korean Nuclear Societyen
dc.description.sponsorshipKhon Kaen University, KKU: R.G.P.2/248/43; Deanship of Scientific Research, King Faisal University, DSR, KFUen
dc.description.sponsorshipThe authors extend their appreciation to the Deanship of Scientific Research at King Khalid University (KKU) for funding this research through the Research Group Program under the Grant Number : R.G.P.2/248/43 .en
dc.format.mimetypeapplication/pdfen
dc.language.isoenen
dc.publisherKorean Nuclear Societyen
dc.rightsinfo:eu-repo/semantics/openAccessen
dc.sourceNuclear Engineering and Technologyen
dc.subjectEQUIVALENT DOSE RATEen
dc.subjectMONTE CARLO SIMULATIONen
dc.subjectNATURAL ROCKSen
dc.subjectRADIOACTIVE WASTE CONTAINERSen
dc.titleThe role of natural rock filler in optimizing the radiation protection capacity of the intermediate-level radioactive waste containersen
dc.typeArticleen
dc.typeinfo:eu-repo/semantics/articleen
dc.typeinfo:eu-repo/semantics/publishedVersionen
dc.identifier.doi10.1016/j.net.2022.05.014-
dc.identifier.scopus85131418190-
local.contributor.employeeTashlykov, O.L., Ural Federal university, 19 Mira St, Yekaterinburg, 620002, Russian Federationen
local.contributor.employeeAlqahtani, M.S., Department of Radiological Sciences, College of Applied Medical Sciences, King Khalid University, Abha, 61421, Saudi Arabia, BioImaging Unit, Space Research Centre, Department of Physics and Astronomy, University of Leicester, Leicester, LE1 7RH, United Kingdomen
local.contributor.employeeMahmoud, K.A., Ural Federal university, 19 Mira St, Yekaterinburg, 620002, Russian Federation, Nuclear Materials Authority, Cairo, El-Maadi, P.O. Box 530, Egypten
local.description.firstpage3849-
local.description.lastpage3854-
local.issue10-
local.volume54-
dc.identifier.wos000869040500012-
local.contributor.departmentUral Federal university, 19 Mira St, Yekaterinburg, 620002, Russian Federationen
local.contributor.departmentDepartment of Radiological Sciences, College of Applied Medical Sciences, King Khalid University, Abha, 61421, Saudi Arabiaen
local.contributor.departmentBioImaging Unit, Space Research Centre, Department of Physics and Astronomy, University of Leicester, Leicester, LE1 7RH, United Kingdomen
local.contributor.departmentNuclear Materials Authority, Cairo, El-Maadi, P.O. Box 530, Egypten
local.identifier.pure30895831-
local.identifier.eid2-s2.0-85131418190-
local.identifier.wosWOS:000869040500012-
Располагается в коллекциях:Научные публикации ученых УрФУ, проиндексированные в SCOPUS и WoS CC

Файлы этого ресурса:
Файл Описание РазмерФормат 
2-s2.0-85131418190.pdf1,8 MBAdobe PDFПросмотреть/Открыть


Все ресурсы в архиве электронных ресурсов защищены авторским правом, все права сохранены.