Summary of advanced LMR (Liquid Metal Reactor) evaluations PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor)

Summary of advanced LMR (Liquid Metal Reactor) evaluations [electronic resource] : PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor)

In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Power Reactor Inherently Safe Module (PRISM) (Berglu...

Full description

Saved in:
Bibliographic Details
Online Access: Online Access
Corporate Authors: U.S. Nuclear Regulatory Commission (Researcher), Brookhaven National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Las Vegas. Nev. : Oak Ridge, Tenn. : U.S. Department of Energy Yucca Mountain Site Characterization Project ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1989.
Subjects:
Safety.
Design.
Hydraulics.
Computerized Simulation.
Deformation.
Mathematical Models.
Reactor Safety.
Liquid Metal Cooled Reactors.
Fluid Flow.
Simulation.
Lmfbr Type Reactors.
M Codes.
After-heat Removal.
Mechanics.
Energy Transfer.
L Codes.
Pipes.
Computer Codes.
Reactivity.
Research Programs.
Reactor Accidents.
Fluid Mechanics.
Energy Systems.
Breeder Reactors.
Epithermal Reactors.
Reactor Shutdown.
Cooling Systems.
Reactors.
Pumps.
R Codes.
Removal.
Fbr Type Reactors.
Swelling.
Heat Transfer.
Shutdown.
Fast Reactors.
Control Elements.
Loss Of Coolant.
Scram.
Reactor Components.
Reactor Cooling Systems.
Accidents.
Feedback.
General Studies Of Nuclear Reactors.

Internet

Online Access

Online

Holdings details from Online
Call Number: E 1.99: bnl-nureg--52197
E 1.99: bnl-nureg--52197 Available

Similar Items