Improvement of neutronic performance of a catalyzed (D,D) driven hybrid reactor using various moderators and coolants materials

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dc.authorscopusid6603427938
dc.authorscopusid7003423752
dc.authorscopusid6603381007
dc.authorscopusid6507158191
dc.contributor.authorÜnalan, Sebahattin
dc.contributor.authorYapici, Hüseyin
dc.contributor.authorÖzceyhan, Veysel
dc.contributor.authorÇürüttü, Ilyas
dc.date.accessioned2024-09-19T15:49:54Z
dc.date.available2024-09-19T15:49:54Z
dc.date.issued1998
dc.departmentHatay Mustafa Kemal Üniversitesien_US
dc.description.abstractIn this study, improvement of neutronic performance by means of various coolants/ moderators (Be, Pb, C, BeF2, H2O, Li2BeF4, and D2O) inserted between the fusion plasma chamber and the fissile zone of a catalyzed (D,D) driven hybrid reactor was investigated. The fissile zone is considered to be cooled with gas coolants (He, CO2, and air). The neutronic calculations were carried out for different thickness of the coolant/moderator zone (DR). In addition, in order to compare with coolant/moderator zone, the calculations were also repeated for the zone without coolant/moderator. Our calculations has proved that Be, D2O, BeF2, and C showed better performance than other materials in terms of new fuel breeding (239Pu) and increased energy production. In the case of use of coolant and moderator materials in the hybrid blanket, energy production in the fissile zone with Be, D2O, BeF2, and C inserted between the plasma chamber and the fissile zone increased in comparison with the case without moderator/ coolant (void case). According to the calculations, this energy increase reaches a maximum value at a certain DR. For Be, D2O, BeF2, and C, these maximum values expressed as blanket energy multiplication ratio (M) are: 9.79, 11.05,7.5, and 7.2 times that of a (D,D) fusion neutron energy at DR = 28, 45, 48, and 40 cm, respectively. Whereas, the M value for zone without moderator/coolant material is about 4.5 at the same DR values. 239Pu breeding capability of the hybrid blanket showed a similar trend as to energy released in the fissile zone, and maximum 239Pu breeding values are reached at DR < 20 cm. 239Pu nuclides breeding per (D,D) fusion neutron are calculated as 1.05, 1.35, 1.3, 1.28, and 0.5 for C, Be, BeF2, D2O, and void case, respectively. These values are very attractive in terms of rejuvenation of LWR and CANDU spent fuels and enrichment of fertile fuel such as 238U and 232Th in the hybrid blanket as sources for the nuclear fuel requirement of present-day LWR and CANDU reactors. As a result of these calculations, it is recommended that the DR value be about 30 cm in order to reach optimum energy production and new fuel breeding with C, Be, BeF2, and D2O coolants/moderators.en_US
dc.identifier.endpage46en_US
dc.identifier.issn2193-567X
dc.identifier.issue1Aen_US
dc.identifier.scopus2-s2.0-0032398605en_US
dc.identifier.scopusqualityQ1en_US
dc.identifier.startpage35en_US
dc.identifier.urihttps://hdl.handle.net/20.500.12483/15481
dc.identifier.volume23en_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherKing Fahd University of Petroleum and Mineralsen_US
dc.relation.ispartofArabian Journal for Science and Engineeringen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.titleImprovement of neutronic performance of a catalyzed (D,D) driven hybrid reactor using various moderators and coolants materialsen_US
dc.typeArticleen_US

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