The feasibility of using 3He-3He fuel in a fusion reactor

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dc.contributor.authorBahmani, Javad
dc.contributor.departmentOthertr_TR
dc.contributor.facultyOthertr_TR
dc.date.accessioned2022-01-11T11:38:22Z
dc.date.available2022-01-11T11:38:22Z
dc.date.issued2019
dc.description.abstractThe possibilities of using advanced aneutronic fuels such as 3He3He for a clean and efficient fusion power generation are regarded as the most important topics in nuclear engineering. This fuel is completely neutron-free thus, no material activation inside the fusion reactor and no dangerous consequence of accidental radioactive release occurs but it requires high demanding conditions for present-day technology. The investigations show that the radiation power losses are the main problems in the use of this fuel in a fusion reactor. The losses have a principal role in determining the operating temperature of this fuel. The results demonstrate that even under almost optimistic operating conditions, the bremsstrahlung loss power is more than fusion power. To dominate the bremsstrahlung radiation, it would be desired to reduce the electron temperature less than their normal equilibrium values. To improve the performance of 3He3He fusion reactor and to minimize bremsstrahlung and synchrotron radiation, it is essential that the energy transmitted from ions to electrons is minimized. When the electron temperature is low enough, the bremsstrahlung loss is manageable; however, the ionelectron energy transfer rate is very large. The studies indicate that the reduction in the bremsstrahlung power fraction is more useful than the reduction in the ion-electron energy transfer fraction. To restrict he bremsstrahlung power to logical theory level (less than half the fusion power), it is essential to reduce the ion-electron energy transfer rate to the possible minimum in 3He3He fuel.tr_TR
dc.description.indexYoktr_TR
dc.identifier.endpage7tr_TR
dc.identifier.issn/e-issn2147-7736
dc.identifier.issn/e-issn2148-3981
dc.identifier.issue01tr_TR
dc.identifier.startpage1tr_TR
dc.identifier.urihttp://hdl.handle.net/20.500.12575/77038
dc.identifier.volume06tr_TR
dc.language.isoentr_TR
dc.publisherAnkara Üniversitesi Nükleer Bilimler Enstitüsütr_TR
dc.relation.journalJournal of Nuclear Sciencestr_TR
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Başka Kurum Yazarıtr_TR
dc.subjectFusiontr_TR
dc.subjectReactortr_TR
dc.subjectFueltr_TR
dc.subjectRadiationtr_TR
dc.subjectPowertr_TR
dc.titleThe feasibility of using 3He-3He fuel in a fusion reactortr_TR
dc.typeArticletr_TR

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