Published 1983
| Version v1
Journal article
The modeling of heat transfer in a degraded BWR core
- 1. Department of Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY
Description
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
Additional details
Publishing Information
- Journal Title
- AIChE Symp. Ser.
- Journal Volume
- 79
- Journal Issue
- 225
- Series
- AIChE Symp. Ser.
- Journal Page Range
- 284-289
- ISSN
- 0065-8812
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15033361
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTROL ELEMENTS; CONVECTION; HEAT TRANSFER; HYDROGEN; MELTDOWN; MELTING; NUCLEAR FUELS; OXIDATION; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR CORE DISRUPTION; REACTOR CORES; STAINLESS STEELS; THERMAL CONDUCTION; THERMAL RADIATION; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; FUELS; HIGH ALLOY STEELS; 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