The modeling of heat transfer in a degraded BWR core

Journal Article · Sat Jan 01 00:00:00 EST 1983 · AIChE Symp. Ser.; (United States)

OSTI ID:5420594

Podowski, M; Lamey, Jr, R T; Taleyarkhan, R

This paper presents a degraded BWR core heat transfer model for the analysis of accidents leading to core meltdown. The model accounts for conduction, radiation and convection heat transfer, and evaluates such nodal quantities as the regional temperatures and/or melting rates of the fuel, clad, channel boxes and control rods, the zinc and stainless steel oxidation, and the hydrogen generation rates.

• Research Organization: Department of Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY
• OSTI ID: 5420594
• Journal Information: AIChE Symp. Ser.; (United States), Vol. 79:225
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR CORE DISRUPTION
REACTOR CORES
HEAT TRANSFER
MELTDOWN
CONTROL ELEMENTS
CONVECTION
HYDROGEN
MELTING
NUCLEAR FUELS
OXIDATION
REACTOR ACCIDENTS
REACTOR CHANNELS
STAINLESS STEELS
THERMAL CONDUCTION
THERMAL RADIATION
ZIRCONIUM
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ELECTROMAGNETIC RADIATION
ELEMENTS
ENERGY SOURCES
ENERGY TRANSFER
FUELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
NONMETALS
PHASE TRANSFORMATIONS
RADIATIONS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
STEELS
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled