Three-dimensional thermal analysis of a baseline spent fuel repository

Conference · Thu Jun 05 04:00:00 EDT 1980

OSTI ID:5039272

Altenbach, T J; Lowry, W E

A three-dimensional thermal analysis has been performed using finite difference techniques to determine the near-field response of a baseline spent fuel repository in a deep geologic salt medium. A baseline design incorporates previous thermal modeling experience and OWI recommendations for areal thermal loading in specifying the waste form properties, package details, and emplacement configuration. The base case in this thermal analysis considers one 10-year old PWR spent fuel assembly emplaced to yield a 36 kw/acre (8.9 w/m/sup 2/) loading. A unit cell model in an infinite array is used to simplify the problem and provide upper-bound temperatures. Boundary conditions are imposed which allow simulations to 1000 years. Variations studied include a comparison of ventilated and unventilated storage room conditions, emplacement packages with and without air gaps surrounding the canister, and room cool-down scenarios with ventilation following an unventilated state for retrieval purposes. At this low power level ventilating the emplacement room has an immediate cooling influence on the canister and effectively maintains the emplacement room floor near the temperature of the ventilating air. The annular gap separating the canister and sleeve causes the peak temperature of the canister surface to rise by 10/sup 0/F (5.6/sup 0/C) over that from a no gap case assuming perfect thermal contact. It was also shown that the time required for the emplacement room to cool down to 100/sup 0/F (38/sup 0/C) from an unventilated state ranged from 2 weeks to 6 months; when ventilation initiated after times of 5 years to 50 years, respectively. As the work was performed for the Nuclear Regulatory Commission, these results provide a significant addition to the regulatory data base for spent fuel performance in a geologic repository.

• Research Organization: California Univ., Livermore (USA). Lawrence Livermore Lab.
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5039272
• Report Number(s): UCRL-84153; CONF-801102-14
• Country of Publication: United States
• Language: English

Related Subjects

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54 ENVIRONMENTAL SCIENCES
CALCULATION METHODS
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DATA
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ENERGY TRANSFER
FINITE DIFFERENCE METHOD
GEOLOGIC DEPOSITS
HEAT TRANSFER
INFORMATION
ITERATIVE METHODS
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MATHEMATICAL MODELS
NUMERICAL DATA
NUMERICAL SOLUTION
PWR TYPE REACTORS
RADIOACTIVE WASTE DISPOSAL
REACTORS
SALT DEPOSITS
SPATIAL DEPENDENCE
SPENT FUEL STORAGE
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TEMPERATURE MEASUREMENT
THEORETICAL DATA
THERMAL ANALYSIS
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WATER COOLED REACTORS
WATER MODERATED REACTORS