Projected spent fuel storage requirements

Technical Report · Wed Mar 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/6654413· OSTI ID:6654413

Boegel, A J; White, M K; Willingham, C E

This analysis identifies the post-reactor basin storage capacity requirements between now and 1990 for various combinations of utility actions in order to establish the full range of possible storage requirements. The combined actions of reracking reactor basins, transferring spent fuel within utilities, and relaxing the policy of reserving reactor basin capacity for a full core discharge are insufficient to meet pre-1985 spent fuel storage capacity requirements. Additional storage capacity is required before 1985 for at least 1000 BWR assemblies and 2000 PWR assemblies. Storage capacity must be provided for a minimum of 12,000 BWR assemblies and 7,000 PWR assemblies by 1990. If none of the possible industry actions are taken, additional storage capacity is required for over 23,000 BWR and 17,000 PWR assemblies before 1985 and over 63,000 BWR and 40,000 PWR assemblies by 1990. The amount of spent fuel which would be shipped to a post reactor basin storage facility between 1985 and 1990 depends on whether utilities continue the activities and policies required to meet spent fuel storage requirements before 1985 (no full core reserve, intra-utility fuel shipments) or seek to regain their pre-storage shortage posture (full core reserve capacity, no intra-utility fuel shipments). If utilities take the former approach, storage capacity is required between 1985 and 1990 for approximately 11,000 BWR assemblies and 5,000 PWR assemblies. If the latter philososphy prevails, storage capacity must be provided between 1895 and 1990 for approximately 27,000 BWR assemblies and 23,000 PWR assemblies.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 6654413
• Report Number(s): PNL-2564
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BWR TYPE REACTORS
FORECASTING
FUEL POOLS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
SPENT FUEL STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS