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FAST FLUX TEST FACILITY. Quarterly Technical Report, June--August 1969. [electronic resource]

Fast Test Reactor/fuels For, Irradiation Testing Of; Fast Test Reactor/fuels For, Processing And Fabrication Of; Reactor Fuels/development Of Ftr Mixed Oxide, During July To August 1969; Fast Flux Test Facility/fuel Element Radiation Testing; Stainless Steel/radiation Effects On Fuel Element Claddin...

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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, 1969.
Subjects:
Design.
Coolant Loops.
Control.
Reactor Core.
Reactor Safety.
Performance.
Instruments.
Powders.
Radiation Effects.
Sampling.
Stainless Steel-304.
Pipes.
Fuels.
Remote Handling.
Sodium.
Welding.
Ftr.
Metal Cooled Reactors.
Fabrication.
Boron Carbides.
Stainless Steels.
Stainless Steel-316.
Burnup.
Fftf.
Heat Transfer.
Fuel Cans.
Liquid Flow.
Accidents.
Research Reactors.
Fission Products.

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Call Number: E 1.99:bnwl--1174
E 1.99:bnwl--1174 Available

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