Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code

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dc.authoridKara, Ayhan/0000-0001-9224-9601
dc.authoridKorkut, Hatun/0000-0002-6459-996X
dc.authoridKORKUT, TURGAY/0000-0002-1333-6123
dc.contributor.authorKorkut, T.
dc.contributor.authorKara, A.
dc.contributor.authorKorkut, H.
dc.date.accessioned2025-03-23T19:26:39Z
dc.date.available2025-03-23T19:26:39Z
dc.date.issued2016
dc.departmentSinop Üniversitesi
dc.description.abstractUltra High Temperature Ceramics (UHTCs) have low density and high melting point. So they are useful materials in the nuclear industry especially reactor core design. Three UHTCs (silicon carbide, vanadium carbide, and zirconium carbide) were evaluated as the nuclear fuel cladding materials. The SERPENT Monte Carlo code was used to model CANDU, PWR, and VVER type reactor core and to calculate burnup parameters. Some changes were observed at the same burnup and neutronic parameters (keff, neutron flux, absorption rate, and fission rate, depletion of U-238, U-238, Xe-135, Sm-149) with the use of these UHTCs. Results were compared to conventional cladding material zircalloy.
dc.identifier.doi10.3139/124.110580
dc.identifier.endpage608
dc.identifier.issn0932-3902
dc.identifier.issue6
dc.identifier.scopus2-s2.0-85017651126
dc.identifier.scopusqualityQ3
dc.identifier.startpage599
dc.identifier.urihttps://doi.org/10.3139/124.110580
dc.identifier.urihttps://hdl.handle.net/11486/4751
dc.identifier.volume81
dc.identifier.wosWOS:000391425100002
dc.identifier.wosqualityQ4
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherCarl Hanser Verlag
dc.relation.ispartofKerntechnik
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.snmzKA_WOS_20250323
dc.subjectBurnup Calculations
dc.titleEffect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code
dc.typeArticle

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