MSRE DESIGN AND OPERATIONS REPORT. PART V-A. SAFETY ANALYSIS OF OPERATION WITH $sup 233$U.

MSRE DESIGN AND OPERATIONS REPORT. PART V-A. SAFETY ANALYSIS OF OPERATION WITH $sup 233$U. [electronic resource]

Hastelloy N/Mechanical Properties Of Irradiated; Molten Salt Reactor Experiment/Safety Analyses For Uranium-233 Fueled; Molten Salt Reactor Experiment/Piping And Containers In, Use Of Hastelloy-N For; Molten Salt Reactor Experiment/Operations History Of, Total; Uranium Isotopes U-233/ Production For...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (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, 1968.
Subjects:
Analysis.
Chromium Alloys.
Containment.
Control Elements.
Design.
Fuels.
Hastelloy.
Irradiation.
Leaks.
Loading.
Mechanical Properties.
Molybdenum Alloys.
Msre.
Neutrons.
Nickel Alloys.
Numericals.
Operation.
Pipes.
Production.
Reactivity.
Reactor Safety.
Reactors.
Response.
Rods.
Safety.
Salts.
Sensitivity.
Uranium 233.
Uranium 235.
Uses.
N38180* > Power Reactor Development > Safety & Siting.

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Call Number: E 1.99:ornl-tm--2111
E 1.99:ornl-tm--2111 Available

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