Published 1986 | Version v1
Book Metadata-only

Relocation of molten zircaloy in CANDU fuel-element clusters under severe accident conditions

Creators

  • 1. Atomic Energy of Canada Ltd., Whiteshell Nuclear Research Establishment

Description

Relocation of molten Zircaloy/UO/sub 2/ material has been studied in clusters of three simulated fuel elements heated in a horizontal configuration. The experiments were conducted with different temperature ramp rates to a maximum measured surface temperature of 21000C and different steam flow rates. Hydrogen production was measured as a function of time. The results show bonding of the elements and flow of molten material in the sub-channel region. The relocation of molten Zircaloy is a function of the temperature ramp rate and maximum temperature with the most relocation occurring at the highest ramp rate

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
0-89448-121-5
Imprint Title
Proceedings of the international ANS/ENS topical meeting on thermal reactor safety
Journal Page Range
p. XIX1.1-XIX1.8.

Conference

Title
International ANS/ENS topical meeting on thermal reactor safety.
Dates
2-6 Feb 1986.
Place
San Diego, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18080620
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; CHEMICAL ANALYSIS; CHEMICAL REACTION KINETICS; COMPUTERIZED SIMULATION; DISTRIBUTION; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; HEATING; HELIUM GENERATION; HYDROGEN; HYDROGEN GENERATION; LIQUID METALS; MASS TRANSFER; MELTDOWN; REACTOR SAFETY; TEMPERATURE DEPENDENCE; TEMPERATURE GRADIENTS; TIME DEPENDENCE; URANIUM DIOXIDE; VERY HIGH TEMPERATURE; ZIRCALOY
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; ELEMENTS; FLUIDS; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; KINETICS; LIQUIDS; METALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION EFFECTS; REACTION KINETICS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS