UCRL--84153
Description
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/m2) 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 100F (5.60C) 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 10000C) 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 geological repository
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- CONF-801102--14
Conference
- Title
- ASME winter annual meeting.
- Dates
- 16 - 21 Nov 1980.
- Place
- Chicago, IL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12586102
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING; S58: GEOSCIENCES;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CONTAINERS; DIAGRAMS; FINITE DIFFERENCE METHOD; HEAT TRANSFER; MATHEMATICAL MODELS; PWR TYPE REACTORS; RADIOACTIVE WASTE DISPOSAL; SALT DEPOSITS; SPENT FUEL STORAGE; TEMPERATURE MEASUREMENT; THEORETICAL DATA; THERMAL ANALYSIS; UNDERGROUND DISPOSAL; VENTILATION
- Descriptors DEC
- DATA; ENERGY TRANSFER; GEOLOGIC DEPOSITS; INFORMATION; ITERATIVE METHODS; MANAGEMENT; NUMERICAL DATA; NUMERICAL SOLUTION; REACTORS; STORAGE; WASTE DISPOSAL; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS