Film boiling behavior in a nine rod cluster

Conference · Sun Jan 01 04:00:00 EST 1978

OSTI ID:6526890

Sparks, D T; Stanley, C J; McCardell, R K

Film boiling in a cluster geometry was investigated during a recent test conducted in the Power Burst Facility. Cluster information is necessary to assess the applicability of single rod experimental data used in developing light water reactor fuel rod behavior models. The nine-rod test, part of the Power-Cooling-Mismatch (PCM) Test Series, was designed to investigate the film boiling behavior of a central fuel rod surrounded by fuel rods that were also in the film boiling heat transfer regime. Information obtained provides insight into film boiling fuel rod behavior, in an environment believed to be representative of a power reactor rod during a period of over-power or low-flow operation. The nine test rods were arranged in a 3 x 3 lattice with spacing typical of a PWR cluster. Except for fuel enrichment and overall length, the rods were of PWR design.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6526890
• Report Number(s): CONF-781105-12
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
FILM BOILING
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
PBF REACTOR
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
TANK TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS