REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, SEPTEMBER 1961
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, SEPTEMBER 1961

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Published: 1961

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BS>Data from examination of blade-type control rods which were used in BORAX are discussed. Operation and maintenance of EBWR is outlined. In work on Borax V, modifications for easier installation of reactor and components is outlined followed by discussion of superheat fuel element development, and fabrication of various reactor components. Borax reactor design is also reported along with information on development and testing. In research on sodiumcooled reactors, activities are summarized in the LPR III and LPR IV programs along with developmental work on EBR I and II. Studies on reactor safety are reported and activities in a program of nuclear technology and general support are outlined. (J.R.D.).

Reactor Development Program Progress Report, August 1961
Reactor Development Program Progress Report, August 1961

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Published: 1961

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Progress is reviewed on the following reactors: EBWR; Borax-V; ZPR-III- ZPR-VI; ZPR-IX; EBR-I; and EBR-II. An outline of fast and slow reactor safety studies in TREAT is presented. Progress is also reported in applied nuclear and reactor physics; development of reactor fuels, materials, and components; heat engineering technology; separation processes; and advanced reactor concepts. (T.F.H.).

Reactor Development Program Progress Report, December 1962
Reactor Development Program Progress Report, December 1962

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Published: 1963

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Research and development progress is reported on water-cooled reactors, liquid-metal-cooled reactors, general reactor technology, plutonium-recycle reactor program, advanced systems research and development, and nuclear safety. (M.C.G.).

Reactor Development Program Progress Report, June 1962
Reactor Development Program Progress Report, June 1962

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Published: 1962

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ABS>Research and development progress is reported on water-cooled reactors, liquid metal-cooled reactors, general reactor technology, plutonium recycle, advance systems research and development, and nuclear safety. Topics covered include the EBWR, BORAX-V, EBR-I, EBR-II, FARET, applied reactor physics, reactor fuels development, reactor materials development, reactor components development, heat engineering and fluid flow, chemical separations, Argonne Advanced Research Reactor, subcritical reactor as substitute for isotope sources, thermal reactor safety studies, fast reactor safety studies, and direct conversion studies. (M.C.G).