The various microscopic cross-section for uranium-235 and incident thermal neutron. Typical Values of Microscopic Cross-sections Uranium 235 is a fissile isotope , and its fission cross-section for thermal neutrons is about 585 barns (for 0.0253 eV neutron). For fast neutrons, its fission cross-section is on the order of b See more

Learn MoreIf I remember correctly, it's something to do with the chance that a U235 atom will absorb a neutron (as opposed to it causing fission). Press J to jump to the feed. Press question mark to learn the rest of the keyboard shortcuts. Search within r/ExplainLikeImPHD. r/ExplainLikeImPHD.

Learn MoreCross section (barns) total absorption elastic gamma production. ENDF/B-IV U-235 Heating 0 5 10 15 20 Energy (MeV) 10 20 30 40 50 60 70 Heating (MeV/reaction) heating. ENDF/B-IV U-235

Learn MoreDownload scientific diagram | 2 Microscopic production cross section of U-235 from publication: Application of high performance computing in lattice physics code VISWAM | High

Learn MorePreparation of microscopic cross sections of U235 for reactor calculations Preparation of microscopic cross section of uranium 235 for high temperature reactor calculations, Document ID, 19660021783, Document Type, Contractor Report (CR) Authors, Drawbaugh, D. W. (Westinghouse Electric Corp. Pittsburgh, PA, United States)

Learn MoreEnglish: Energy dependence of the fission cross section of U235. Date, 1 January 2009. Source, Plot made with Origin software package on my PC.

Learn MoreThe third column contains values of the absorption cross section (Ja at the The Resonance Fission Integrals of U235, PU239, and PU241. Nuclear.

Learn Morevalues and errors of the microscopic average cross-sections in the uranium-235 thermal fission neutron speet- -\ This evaluation has been done in a way as independently as possible of any assumption regarding differential nuclear data, but the interrelations are indicated whenever necessary.

Learn Morev). Describe in general terms the variation of absorption cross-section of U-235 and U-238 with neutron energy. 3.3 THE MICROSCOPIC CROSS-. SECTION. Let us have

Learn MoreThe U.S. Department of Energy's Office of Scientific and Technical Information

Learn Morearticle{osti_5297408, title = {Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields}, author = {Fabry, A. and McElroy, W. N. and Kellogg, L. S. and Lippincott, E. P. and Grundl, J. A. and Gilliam, D. M. and Hansen, G. E.}, abstractNote = {This paper is intended to review and critically discuss microscopic integral cross section

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