TYPICAL CHARACTERISTICS OF ADVANCED CORES IN THE DISPERSED FTR. [electronic resource]

Plutonium Carbides/puc--uc, Fuel Elements Of Design Parameters Of Fast Test Reactor 400 Mw Beryllium Oxide (beo)-moderated Core Pin-type; Reactor Fuel Elements/design Parameters For Fast Test Reactor 400 Mw Core Beryllium Oxide (beo)-moderated Plutonium Carbide (puc)--uranium Carbide (uc) Pin- Type;...

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Bibliographic Details

Online Access:	Online Access
Corporate Authors:	Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1968.
Subjects:	Ftr. Beryllium Oxides. Analysis. Reactor Core. Power. Configuration. Fuels. Moderators. Reactivity. Uranium Carbides. Fuel Elements. Plutonium Carbides. Research Reactors.