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Heat transfer modeling of dry spent nuclear fuel storage facilities

Conference ·
OSTI ID:20002517
The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geologic codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geologic repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.
Research Organization:
Westinghouse Savannah River Technology Center, Aiken, SC (US)
Sponsoring Organization:
US Department of Energy
OSTI ID:
20002517
Report Number(s):
CONF-990805--
Country of Publication:
United States
Language:
English

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