Published 2001
| Version v1
Miscellaneous
Open
Thermalhydraulic phenomena governing the quenching of hot rods, and existing models
Creators
- 1. CEA-Grenoble, DEN/DTP/SMTH (France)
Description
After a core dry-out and a period of rod clad overheating, which might occur in some postulated accidental sequences in a PWR, the actuation of safety injections allows to quench the hot rods. Both thermal and mechanical processes control the phenomenon of quenching. Quenching first requires that liquid water is present to release the heat stored in the rod. When water is present, a pre-cooling of the clad is also required before quenching. (author)
Availability note (English)
Available from INIS in electronic formFiles
35002708.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-FR--1693
Conference
- Title
- Progress and future trends in core degradation modeling
- Acronym
- ICARE/CATHARE seminar
- Dates
- 21-23 Nov 2001
- Place
- Cadarache (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 35002708
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLING; CORE SPRAY SYSTEMS; DROPLETS; FUEL RODS; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; QUENCHING; STEAM; THERMAL CONDUCTIVITY; WATER
- Descriptors DEC
- ACCIDENTS; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ELEMENTS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; PARTICLES; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Also available from: IRSN/DRS - Bat. 229, Centre d'Etudes de Cadarache, F-13115 Saint-Paul-lez-Durance Cedex