Reflooding of tight lattice bundles

Journal Article · Fri Jul 01 00:00:00 EDT 1994 · Nuclear Technology; (United States)

OSTI ID:7054772

Veteau, J M; Digonnet, A; Deruaz, R ^[1]

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1. Commissariat a l'Energie Atomique, Grenoble (France). Centre d'Etudes Nucleaires de Grenoble

Results regarding analytical bottom reflooding experiments in a 37- and a 127-heater rod bundle are presented for two different tight lattices. A comparison between these two geometries and with the standard pressurized water reactor (PWR) array shows a degradation of cooling efficiency when the cross section of the subchannels is decreased. The core heat sinks (guide thimbles and water tubes'') are seen to have a noticeable influence on the overall cooling of the bundle, and it is confirmed that a combined top/bottom injection does not significantly improve cooling efficiency. Calculations with CATHARE 1.3 code adjusted for the standard PWR array are presented (zero heat sinks), but results have to be confirmed over a wider range of parameters.

• OSTI ID: 7054772
• Journal Information: Nuclear Technology; (United States), Vol. 107:1; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT CLUSTERS
COOLING
PWR TYPE REACTORS
C CODES
DATA ANALYSIS
DESIGN
FLUID INJECTION
LOSS OF COOLANT
REACTOR LATTICES
REACTOR SAFETY
SHROUDS
THEORETICAL DATA
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
INFORMATION
NUMERICAL DATA
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled