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absorption cross section Atomic Enrichment average fast flux Axial Neutron Flux Borated Center of Core critical loading decay constant Design Full Power design power Design temperature diphenyl volume ratio equation FACTOR FOR WIRE fast diffusion constant fast fission factor Fermi Age fission product Flux at Center Flux at Midplane fuel plates Function of Atomic infinite diphenyl reflector light water macroscopic absorption cross macroscopic cross section maximum to average maximum xenon metal to diphenyl NEAREST NEIGHBOR neutron reproduction factor NEUTRON SHIELDING neutrons/(cm2)(sec Old core Override of Maximum Override Temperature Plate Fuel Elements promethium radial radius reflector savings Resonance Escape Probability shown in Fig slightly enriched slow flux stainless steel Stainless Steel-Diphenyl Reactor steel to diphenyl temperature override thermal neutron two-group U235 loading Unborated unburned boron uranium meat volume average Wire and Plate Wire fuel elements xenon and samarium zirconium