Natural circulation in simulated LMFBR fuel assemblies

Natural circulation in simulated LMFBR fuel assemblies [electronic resource]

Natural circulation experiments have been performed using simulated liquid metal fast breeder reactor fuel assemblies in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility, an engineering-scale sodium loop. Objective of these tests has been to provide experimental data under conditions tha...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1985.
Subjects:
Convection.
Energy Systems.
Breeder Reactors.
Epithermal Reactors.
Mass Transfer.
Coolant Loops.
Cooling Systems.
Reactors.
Liquid Metal Cooled Reactors.
Natural Convection.
Lmfbr Type Reactors.
Removal.
Fbr Type Reactors.
After-heat Removal.
Heat Transfer.
Energy Transfer.
Fast Reactors.
Reactor Components.
Rhr Systems.
Reactor Cooling Systems.
Fuel Assemblies.
Reactor Safety Experiments.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99:conf-850420-4
E 1.99:conf-850420-4 Available

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