Properties of reactor fuel rod materials at high temperatures: Final summary report: Severe Core Damage Property Tests Program
This report summarizes work sponsored by the US Nuclear Regulatory Commission Division of Accident Evaluation to investigate those physical properties that are needed to predict the behavior of fuel-rod assemblies during a loss-of-coolant accident. The results include a determination of the oxidation kinetics of Zircaloy and Zircaloy-uranium oxide mixtures in steam and steam-hydrogen gas mixtures at 1300 to 2400C, viscosity measurements of zirconium-oxide mixtures at 1800 to 2100C, an estimate of the heat of reaction for the dissolution of uranium oxide by molten zirconium at 2000C, and thermal diffusivity measurements on prereacted Zircaloy-uranium oxide mixtures at 800 to 1500C.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Accident Analysis
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6439003
- Report Number(s):
- NUREG/CR-4891; PNL-6164; ON: TI87013281
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
LOSS OF COOLANT
NUCLEAR POWER PLANTS
FUEL RODS
REACTOR MATERIALS
URANIUM OXIDES
OXIDATION
ZIRCALOY
ZIRCONIUM OXIDES
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
VERY HIGH TEMPERATURE
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHEMICAL REACTIONS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MATERIALS
MECHANICS
NUCLEAR FACILITIES
OXIDES
OXYGEN COMPOUNDS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
THERMAL POWER PLANTS
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
ZIRCONIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
220300 - Nuclear Reactor Technology- Fuel Elements
360205 - Ceramics
Cermets
& Refractories- Corrosion & Erosion
360105 - Metals & Alloys- Corrosion & Erosion
36 MATERIALS SCIENCE
LOSS OF COOLANT
NUCLEAR POWER PLANTS
FUEL RODS
REACTOR MATERIALS
URANIUM OXIDES
OXIDATION
ZIRCALOY
ZIRCONIUM OXIDES
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
VERY HIGH TEMPERATURE
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHEMICAL REACTIONS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MATERIALS
MECHANICS
NUCLEAR FACILITIES
OXIDES
OXYGEN COMPOUNDS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
THERMAL POWER PLANTS
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
ZIRCONIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
220300 - Nuclear Reactor Technology- Fuel Elements
360205 - Ceramics
Cermets
& Refractories- Corrosion & Erosion
360105 - Metals & Alloys- Corrosion & Erosion