Published 1988
| Version v1
Book
Bottom reflooding of a 37 tight lattice rod bundle for future PWRs
Creators
- 1. Centre d'Etudes Nucleaires de Grenoble, 85 X - 38041 Grenoble Cedex (France)
Description
Results regarding preliminary reflooding experiments with a 37 rod bundle in the geometry of future PWRs (coolant-to-fuel ratio equal to 1.1) are presented. It is shown that overall quench times and maximum cladding temperatures exhibit the same parametric trends as already observed for standard PWR. Comparison to experiment performed with standard PWR geometry as well as with a very tightened lattice (coolant-to-fuel ratio equal to .6) showed that, under the same initial and boundary conditions, the smaller the lattice, the more difficult the cooling. Reasons for such a tendency are analyzed. First calculations with Cathare code 1.3, adjusted to be confirmed over a wider range of parameters
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 89448-1460-0
- Imprint Title
- Proceedings of the international topical meeting on safety of next generation power reactors
- Imprint Pagination
- 933 p.
- Journal Page Range
- p. 779-785.
Conference
- Title
- American Nuclear Society topical meeting on the safety of next generation power reactors.
- Dates
- 1-5 May 1988.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22023463
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; QUENCHING; REACTOR COOLING SYSTEMS; REACTOR SAFETY
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT TREATMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-880506--.