Neutron Production Cross-Section and Geant4 Calculations of the Structural Fusion Material Co-59 for (alpha,xn) and (gamma,xn) Reactions

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dc.contributor.authorDemir, B.
dc.contributor.authorKaplan, A.
dc.contributor.authorCapali, V.
dc.contributor.authorOzdogan, H.
dc.contributor.authorSarpun, I. H.
dc.contributor.authorAydin, A.
dc.contributor.authorTel, E.
dc.date.accessioned2020-06-25T18:13:15Z
dc.date.available2020-06-25T18:13:15Z
dc.date.issued2015
dc.departmentKırıkkale Üniversitesi
dc.descriptionOZDOGAN, Hasan/0000-0001-6127-9680; SARPUN, Ismail Hakki/0000-0002-9788-699X
dc.description.abstractRecent advances in technology and computer sciences give us simplicity to investigate phenomena of nuclear physics. Scientists have improved various nuclear reaction codes such as Talys, Alice/ASH, Cem95, Empire, Geant4 and Fluka. These programs give us chance to calculate crucial quantity like reaction cross-section, energy spectrum of out-going particles, stopping power and penetrating distances in target material. The stopping power of alpha in Co-59 material is acquired as it has helpful applications of shielding and choosing the proper thickness of the target. Evaluation of the reaction cross-section data is very important to various applications such as improvement structural material, reactor design and radioisotopes production. In this study, we calculated the neutron production cross-sections of Co-59 using TALYS 1.6 and EMPIRE 3.1 codes for different level density models. Penetrating distances and stopping powers have been calculated for the alpha particles taking into consideration all possible reactions in Co-59 using GEANT4 simulation program. The obtained (alpha,xn) and (gamma,xn) reactions (x = 1, 2, 3) cross-section values have been compared with the each other and against the experimental nuclear reaction data existing in EXFOR database.en_US
dc.identifier.citationclosedAccessen_US
dc.identifier.doi10.1007/s10894-015-9860-4
dc.identifier.endpage641en_US
dc.identifier.issn0164-0313
dc.identifier.issn1572-9591
dc.identifier.issue3en_US
dc.identifier.scopus2-s2.0-84939988898
dc.identifier.scopusqualityQ2
dc.identifier.startpage636en_US
dc.identifier.urihttps://doi.org/10.1007/s10894-015-9860-4
dc.identifier.urihttps://hdl.handle.net/20.500.12587/6160
dc.identifier.volume34en_US
dc.identifier.wosWOS:000354202200033
dc.identifier.wosqualityN/A
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherSpringeren_US
dc.relation.ispartofJournal Of Fusion Energy
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectNeutron production cross-sectionen_US
dc.subjectLevel density modelsen_US
dc.subjectGEANT4en_US
dc.subjectStopping poweren_US
dc.subjectCobalten_US
dc.titleNeutron Production Cross-Section and Geant4 Calculations of the Structural Fusion Material Co-59 for (alpha,xn) and (gamma,xn) Reactionsen_US
dc.typeArticle

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