The most general equations for multigroup neutron diffusion in P1 approximation

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dc.contributor.authorŞuhubi, Erdoğan
dc.contributor.authorÖzemre, Ahmed Yüksel
dc.contributor.departmentTAEK-ÇNAEMtr_TR
dc.date.accessioned2017-09-29T06:18:26Z
dc.date.available2017-09-29T06:18:26Z
dc.date.issued1962
dc.descriptionTENMAK D.N.. 10304tr_TR
dc.description.abstractStarting from the general transport equation and within the limits of P1 approximation, a set of coupled second order partial integro-differential equations is obtained. These equations consider the effect of m groups of retarded neutrons and contain both the first and the second derivatives of the neutron fluxes with respect to the time variable.tr_TR
dc.identifier.citationŞuhubi, E. ve Özemre, A. Y. (1962).The most general equations for multigroup neutron diffusion in P1 approximation. İstanbul : T.A.E.C. Çekmece Nuclear Research Center.tr_TR
dc.identifier.urihttp://kurumsalarsiv.tenmak.gov.tr/handle/20.500.12878/589
dc.language.isoengtr_TR
dc.publisherT.A.E.C. Çekmece Nuclear Research Centertr_TR
dc.relation.ispartofseriesT.A.E.C. Çekmece Nuclear Research Center;ÇNAM 3
dc.rightsinfo:eu-repo/semantics/openAccesstr_TR
dc.subjectNeutrons
dc.subjectNötronlar
dc.subjectNeutron diffusiontr_TR
dc.subjectNötron difüzyonutr_TR
dc.titleThe most general equations for multigroup neutron diffusion in P1 approximationtr_TR
dc.typereporttr_TR
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