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NEUTRONIC CONSIDERATIONS IN THE SELECTION OF A DRIVER FUEL FOR THE FAST TEST REACTOR (FTR) [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Main Authors:	Hardie, R.W (Author), Little, W.W. Jr (Author)
Corporate Author:	Battelle Memorial Institute (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1965.
Subjects:	Coating. Fast Test Reactor. Ftr. Fuel Elements. Neutron Flux. Fuels. Plutonium Oxides. Research Reactors. Spectral Shift. Stainless Steels. Performance. Uranium Dioxide. Reactor Technology. Research And Test Reactors.

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Call Number:	E 1.99:bnwl-197
E 1.99:bnwl-197	Available