Preliminary design report for prototypical spent nuclear fuel rod consolidation equipment

Technical Report · Mon Dec 01 04:00:00 EST 1986

DOI:https://doi.org/10.2172/7080253· OSTI ID:7080253

Judson, B F; Maillet, J; O'Neill, G L; Tsitsichvili, J; Tucoulat, D

The purpose of the Prototypical Consolidation Demonstration Project (PCDP) is to develop and demonstrate the equipment system that will be used to consolidate the bulk of the spent nuclear fuel generated in the United States prior to its placement in a geological repository. The equipment must thus be capable of operating on a routine production basis over a long period of time with stringent requirements for safety, reliability, productivity and cost-effectiveness. Four phases are planned for the PCDP. Phase 1 is the Preliminary Design of generic consolidation equipment that could be installed at a Monitored Retrievable Storage (MRS) facility or in the Receiving Handling Facility at a geologic repository site. Phase 2 will be the Final Design and preparation of procurement packages for the equipment in a configuration capable of being installed and tested in a special enclosure within the TAN Hot Shop at DOE's Idaho National Engineering Laboratory. In Phase 3 the equipment will be fabricated and then tested with mock fuel elements in a contractor's facility. Finally, in Phase 4 the equipment will be moved to the TAN facility for demonstration operation with irradiated spent fuel elements. 55 figs., 15 tabs.

• Research Organization: General Electric Co., San Jose, CA (USA)
• Sponsoring Organization: DOE/RW
• DOE Contract Number: AC07-86ID12648
• OSTI ID: 7080253
• Report Number(s): DOE/ID/12648-T1; GEFR--00800; ON: DE90008782
• Country of Publication: United States
• Language: English

Related Subjects

050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
052002* -- Nuclear Fuels-- Waste Disposal & Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CLEANING
CONTROL
CUTTING TOOLS
DECONTAMINATION
DESIGN
DIAGRAMS
ECONOMIC ANALYSIS
ECONOMICS
ENGINEERING DRAWINGS
EQUIPMENT
FLOWSHEETS
FUEL ELEMENTS
HIGH-LEVEL RADIOACTIVE WASTES
LABORATORY EQUIPMENT
LIQUID WASTES
MANAGEMENT
MANIPULATORS
MATERIALS
MATERIALS HANDLING EQUIPMENT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PACKAGING
POWER PLANTS
PWR TYPE REACTORS
RADIATION PROTECTION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
REACTOR COMPONENTS
REACTORS
RELIABILITY
REMOTE CONTROL
REMOTE HANDLING
REMOTE HANDLING EQUIPMENT
REPORTING REQUIREMENTS
SAFETY
SPECIFICATIONS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
THERMAL POWER PLANTS
TOOLS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS