Thermomechanical modeling of the spent fuel test - Climax
The Spent Fuel Test-Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep geologic storage of commercially generated spent nuclear-reactor fuel assemblies. One of the primary aspects of the test was to measure the thermomechanical response of the rock mass to the extensive heating of a large volume of rock. Instrumentation was emplaced to measure stress changes, relative motion of the rock mass, and tunnel closures during three years of heating from thermally decaying heat sources, followed by a six month cooldown period. The calculations reported here were performed using the best available input parameters, thermal and mechanical properties, and power levels which were directly measured or inferred from measurements made during the test. This report documents the results of these calculations and compares the results with selected measurements made during heating and cooling of the SFT-C.
- Research Organization:
- Lawrence Livermore National Lab., P.O. Box 808, Livermore, CA 94550
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 59948
- Report Number(s):
- CONF-860609--; ISBN 0-87335-059-6
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
58 GEOSCIENCES
COOLING
FEASIBILITY STUDIES
HEATING
MATHEMATICAL MODELS
MEASURING METHODS
MECHANICAL PROPERTIES
MONITORED RETRIEVABLE STORAGE
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE STORAGE
ROCK MECHANICS
ROCKS
SPENT FUEL ELEMENTS
SPENT FUELS
STRATA MOVEMENT
STRESS ANALYSIS
TEMPERATURE EFFECTS
TESTING
THERMODYNAMIC PROPERTIES
TUNNELS
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