Developments of models for boiling and dryout in LWR debris beds: Chapter 15
Description
The coolability of solid self-heated fuel debris in water is a topic of major interest in probabilistic safety analyses of light water reactors. Many experiments have been undertaken using simulant heating methods and simulant materials for the particulate, to investigate the dependence of the dryout heat flux (i.e. that heating rate at which liquid coolant is no longer able to adequately penetrate the debris bed, such that local temperatures may rise considerably in excess of the coolant's boiling point). The paper considers further developments and applications of these models. The particular topics discussed are (i) the transient approach to dryout for deep beds, (ii) the effect of a gradation in particulate size (i.e. the mean particle diameter varies with position in the bed), and (iii) the inclusion of a dried out layer in a one-dimensional model
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-89448-112-6
- Imprint Title
- Proceedings of the international meeting on light water severe accident evaluation
- Journal Page Range
- p. 3.1.
Conference
- Title
- International meeting on light-water reactor severe accident evaluation.
- Dates
- 28 Aug - 1 Sep 1983.
- Place
- Cambridge, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18014482
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; BWR TYPE REACTORS; CHEMICAL REACTION KINETICS; COOLING; DRYOUT; FISSION PRODUCTS; FUEL-COOLANT INTERACTIONS; HEAT FLUX; LAYERS; MATHEMATICAL MODELS; ONE-DIMENSIONAL CALCULATIONS; PARTICLE SIZE; PARTICLES; PROBABILITY; PWR TYPE REACTORS; REACTOR MATERIALS; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; SIMULATION; TRANSIENTS; WATER; WATER COOLED REACTORS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; ISOTOPES; KINETICS; MATERIALS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POLAR SOLVENTS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTION KINETICS; REACTORS; SAFETY; SIZE; SOLVENTS; THERMAL REACTORS; WATER MODERATED REACTORS