Radiation source terms of MYRRHA reactor components and equipment

dc.authoridVan den Eynde, Gert/0000-0002-4728-4456
dc.authoridStankovskiy, Alexey/0000-0003-1837-023X
dc.authoridcelik, yurdunaz/0000-0002-9211-8510
dc.authorscopusid54384850100
dc.authorscopusid21741121600
dc.authorscopusid55481118000
dc.authorscopusid55960228200
dc.authorscopusid14027391200
dc.authorscopusid7102942712
dc.authorwosidŞahin, Sŭmer/C-6252-2013
dc.contributor.authorŞahin, Sümer
dc.contributor.authorStankovskiy, Alexey
dc.contributor.authorEngelen, Jeroen
dc.contributor.authorVan den Eynde, Gert
dc.contributor.authorSarer, Basar
dc.contributor.authorSahin, Sumer
dc.contributor.otherDepartment of Mechanical Engineering
dc.date.accessioned2024-07-05T14:29:21Z
dc.date.available2024-07-05T14:29:21Z
dc.date.issued2016
dc.departmentAtılım Universityen_US
dc.department-temp[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, Turkeyen_US
dc.descriptionVan den Eynde, Gert/0000-0002-4728-4456; Stankovskiy, Alexey/0000-0003-1837-023X; celik, yurdunaz/0000-0002-9211-8510en_US
dc.description.abstractIn-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.citation2
dc.identifier.doi10.1016/j.ijhydene.2016.01.119
dc.identifier.endpage7220en_US
dc.identifier.issn0360-3199
dc.identifier.issn1879-3487
dc.identifier.issue17en_US
dc.identifier.scopus2-s2.0-84964440080
dc.identifier.startpage7213en_US
dc.identifier.urihttps://doi.org/10.1016/j.ijhydene.2016.01.119
dc.identifier.urihttps://hdl.handle.net/20.500.14411/508
dc.identifier.volume41en_US
dc.identifier.wosWOS:000375886400031
dc.identifier.wosqualityQ1
dc.language.isoenen_US
dc.publisherPergamon-elsevier Science Ltden_US
dc.relation.ispartof17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Istanbul, TURKEYen_US
dc.relation.publicationcategoryKonferans Öğesi - Uluslararası - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectMYRRHAen_US
dc.subjectReactor vesselen_US
dc.subjectMCNPXen_US
dc.subjectActivationen_US
dc.subjectALEPH2en_US
dc.titleRadiation source terms of MYRRHA reactor components and equipmenten_US
dc.typeConference Objecten_US
dspace.entity.typePublication
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relation.isOrgUnitOfPublication.latestForDiscoveryf77120c2-230c-4f07-9aae-94376b6c4cbb

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