Published 1988 | Version v1
Book

Bottom reflooding of a 37 tight lattice rod bundle for future PWRs

  • 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--.