Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor (HFIR) using RELAP5 and TEMPEST Part 2, Interpretation and validation of results.

Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor (HFIR) using RELAP5 and TEMPEST [electronic resource] : Part 2, Interpretation and validation of results.

The RELAP5/MOD2 code was used to predict the thermal-hydraulic behavior of the HFIR core during decay heat removal through boiling natural circulation. The low system pressure and low mass flux values associated with boiling natural circulation are far from conditions for which RELAP5 is well exerci...

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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, 1989.
Subjects:
Hydraulics.
Test Reactors.
Mass Transfer.
Water Moderated Reactors.
Computerized Simulation.
Hfir Reactor.
Isotope Production Reactors.
Fluid Flow.
Simulation.
Equations.
Research And Test Reactors.
After-heat Removal.
Energy Transfer.
Mechanics.
Computer Codes.
Thermal Reactors.
Fluid Mechanics.
Tank Type Reactors.
Water Cooled Reactors.
Reactors.
Enriched Uranium Reactors.
R Codes.
Irradiation Reactors.
Removal.
Heat Transfer.
Pressure Drop.
Research Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:conf-890173-1
E 1.99:conf-890173-1 Available

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