Investigation of neutronic effects in structural material of a hybrid reactor by using the MCNPX Monte Carlo transport code

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.date.accessioned2024-08-04T20:37:46Z
dc.date.available2024-08-04T20:37:46Z
dc.date.issued2013
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn this study, 98-90% Li2BeF4-2-10 % ThF4, 98-90% Li2BeF4-2-10 % UF4, 98-90% Li2BeF4-2-10 % UO2 and 100% Li2BeF4 molten salt-heavy metal was used as fluid. The fluids were used in the liquid first wall, liquid second wall and shield zones of the designed hybrid reactor system. A steel wall of 4 cm thickness is used as structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In the study, the effect of liquid second wall thicknesses (20 cm, 30 cm, 40 cm, 50 cm) on the neutron flux distribution and the parameters of radiation damage according to neutron energy spectrum in the structural material were investigated for the selected fluids. A three-dimensional analysis was done by using the most recent version of the MCNPX-2.7.0 Monte Carlo code and the nuclear data library ENDF/B-VII.en_US
dc.description.sponsorshipInonu University [2012/183]en_US
dc.description.sponsorshipThis work was supported by Inonu University Research fund with the project number 2012/183.en_US
dc.identifier.endpage203en_US
dc.identifier.issn0932-3902
dc.identifier.issue3en_US
dc.identifier.scopus2-s2.0-84882287790en_US
dc.identifier.scopusqualityN/Aen_US
dc.identifier.startpage198en_US
dc.identifier.urihttps://hdl.handle.net/11616/96177
dc.identifier.volume78en_US
dc.identifier.wosWOS:000323402800005en_US
dc.identifier.wosqualityQ4en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherCarl Hanser Verlagen_US
dc.relation.ispartofKerntechniken_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectBreeder Apex Reactoren_US
dc.subjectRadiation-Damageen_US
dc.subjectFusion Breederen_US
dc.subjectHylife-Iien_US
dc.subjectTechnologyen_US
dc.subjectDesignen_US
dc.subjectSystemen_US
dc.subjectFuelen_US
dc.subjectWallen_US
dc.titleInvestigation of neutronic effects in structural material of a hybrid reactor by using the MCNPX Monte Carlo transport codeen_US
dc.typeArticleen_US

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