Radiation Source Terms of Myrrha Reactor Components and Equipment

dc.contributor.author Celik, Yurdunaz
dc.contributor.author Stankovskiy, Alexey
dc.contributor.author Engelen, Jeroen
dc.contributor.author Van den Eynde, Gert
dc.contributor.author Sarer, Basar
dc.contributor.author Sahin, Sumer
dc.date.accessioned 2024-07-05T14:29:21Z
dc.date.available 2024-07-05T14:29:21Z
dc.date.issued 2016
dc.description Van den Eynde, Gert/0000-0002-4728-4456; Stankovskiy, Alexey/0000-0003-1837-023X; celik, yurdunaz/0000-0002-9211-8510 en_US
dc.description.abstract In-vessel structural components of nuclear reactors are subject to prompt and residual neutron and photon activation. The MYRRHA fast spectrum facility, when operated in sub critical mode, suffers additional activation due to a wide range of energetic particles produced in the interactions of 600 MeV-primary protons with matter. The purpose of this work was to assess the source term (activation, heating and induced radiation level) of ex core equipment and components located inside the reactor vessel. Numerous stainless steel samples uniformly distributed inside the vessel have been used to simulate the activation of equipment in order to take into account the perturbation of the neutron spectrum caused by structural materials of components and equipment. The calculated quantities were prompt and residual activation, heating, radiation dose and radiation damage. The calculations were carried out with the ALEPH2 depletion code which invokes the MCNPX code for radiation transport. Copyright (C) 2016, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved. en_US
dc.identifier.doi 10.1016/j.ijhydene.2016.01.119
dc.identifier.issn 0360-3199
dc.identifier.issn 1879-3487
dc.identifier.scopus 2-s2.0-84964440080
dc.identifier.uri https://doi.org/10.1016/j.ijhydene.2016.01.119
dc.identifier.uri https://hdl.handle.net/20.500.14411/508
dc.language.iso en en_US
dc.publisher Pergamon-elsevier Science Ltd en_US
dc.relation.ispartof 17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Istanbul, TURKEY en_US
dc.rights info:eu-repo/semantics/closedAccess en_US
dc.subject MYRRHA en_US
dc.subject Reactor vessel en_US
dc.subject MCNPX en_US
dc.subject Activation en_US
dc.subject ALEPH2 en_US
dc.title Radiation Source Terms of Myrrha Reactor Components and Equipment en_US
dc.type Conference Object en_US
dspace.entity.type Publication
gdc.author.id Van den Eynde, Gert/0000-0002-4728-4456
gdc.author.id Stankovskiy, Alexey/0000-0003-1837-023X
gdc.author.id celik, yurdunaz/0000-0002-9211-8510
gdc.author.scopusid 54384850100
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gdc.author.scopusid 55960228200
gdc.author.scopusid 14027391200
gdc.author.scopusid 7102942712
gdc.author.wosid Şahin, Sŭmer/C-6252-2013
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gdc.collaboration.industrial false
gdc.description.department Atılım University en_US
gdc.description.departmenttemp [Celik, Yurdunaz] Gazi Univ, Inst Sci & Technol, TR-06503 Ankara, Turkey; [Celik, Yurdunaz; Stankovskiy, Alexey; Engelen, Jeroen; Van den Eynde, Gert] CEN SCK, Inst Adv Nucl Syst, Boeretang 200, B-2400 Mol, Belgium; [Sarer, Basar] Gazi Univ, Fac Sci, TR-06500 Ankara, Turkey; [Sahin, Sumer] Atilim Univ, Fac Engn, TR-06836 Ankara, Turkey en_US
gdc.description.endpage 7220 en_US
gdc.description.issue 17 en_US
gdc.description.publicationcategory Konferans Öğesi - Uluslararası - Kurum Öğretim Elemanı en_US
gdc.description.startpage 7213 en_US
gdc.description.volume 41 en_US
gdc.description.wosquality Q1
gdc.identifier.openalex W2283373066
gdc.identifier.wos WOS:000375886400031
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gdc.oaire.sciencefields 0211 other engineering and technologies
gdc.oaire.sciencefields 0202 electrical engineering, electronic engineering, information engineering
gdc.oaire.sciencefields 02 engineering and technology
gdc.openalex.collaboration International
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gdc.opencitations.count 1
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gdc.virtual.author Şahin, Sümer
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