Simulation of Multi Canister Overpack (MCO) Handling Machine Impact with Cask and MCO During Insertion into the Transfer Pit (FDT-137)

Technical Report · Thu Apr 13 04:00:00 EDT 2000

DOI:https://doi.org/10.2172/803037· OSTI ID:803037

BAZINET, G D ^[1]

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1. FFS

The K-Basin Cask and Transportation System will be used for safely packaging and transporting approximately 2,100 metric tons of unprocessed, spent nuclear fuel from the 105 K East and K West Basins to the 200 E Area Canister Storage Building (CSB). Portions of the system will also be used for drying the spent fuel under cold vacuum conditions prior to placement in interim storage. The spent nuclear fuel is currently stored underwater in the two K-Basins. The K-Basins loadout pit is the area selected for loading spent nuclear fuel into the Multi-Canister Overpack (MCO) which in turn is located within the transportation cask. This Cask/MCO unit is secured.in the pit with a pail load out structure whose primary function is lo suspend and support the Cask/MCO unit at.the desired elevations and to protect the unit from the contaminated K-Basin water. The fuel elements will be placed in special baskets and stacked in the MCO that have been previously placed in the cask. The casks will be removed from the K Basin load out areas and taken to the cold vacuum drying station. Then the cask will be prepared for transportation to the CSB. The shipments will occur exclusively on the Hanford Site between K-Basins and the CSB. Travel will be by road with one cask per trailer. At the CSB receiving area the cask will be removed from the trailer. A gantry crane will then move the cask over to the transfer pit and load the cask into the transfer pit. From the transfer pit the MCO will be removed from the cask by the MCO Handling Machine (MHM). The MHM will move the MCO from the transfer pit to a canister storage tube in the CSB. MCOs will be piled two high in each canister Storage tube.

• Research Organization: FFS (US)
• Sponsoring Organization: ENVIRONMENTAL MANAGEMENT (US)
• DOE Contract Number: AC06-96RL13200
• OSTI ID: 803037
• Report Number(s): SNF-6031, Rev.0; EDT-627037
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATION
CASKS
CONTAINERS
DRYING
ELECTRON TUBES
FUEL ELEMENTS
IMAGE STORAGE TUBES
METRICS
NUCLEAR FUELS
PACKAGING
SIMULATION
SPENT FUELS
STORAGE
TRANSPORTATION SYSTEMS
WATER