Disposal of Spent Fuel

Conference · Sun Mar 05 04:00:00 EST 1978

OSTI ID:5193259

Blomeke, J. O. ^[1]; Ferguson, D. E. ^[1]; Croff, A. G. ^[1]

---

1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Based on preliminary analyses, spent fuel assemblies are an acceptable form for waste disposal. The following studies appear necessary to bring our knowledge of spent fuel as a final disposal form to a level comparable with that of the solidified wastes from reprocessing: 1. A complete systems analysis is needed of spent fuel disposition from reactor discharge to final isolation in a repository. 2. Since it appears desirable to encase the spent fuel assembly in a metal canister, candidate materials for this container need to be studied. 3. It is highly likely that some ''filler'' material will be needed between the fuel elements and the can. 4. Leachability, stability, and waste-rock interaction studies should be carried out on the fuels. The major disadvantages of spent fuel as a disposal form are the lower maximum heat loading, 60 kW/acre versus 150 kW/acre for high-level waste from a reprocessing plant; the greater long-term potential hazard due to the larger quantities of plutonium and uranium introduced into a repository; and the possibility of criticality in case the repository is breached. The major advantages are the lower cost and increased near-term safety resulting from eliminating reprocessing and the treatment and handling of the wastes therefrom.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Waste Management Division
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5193259
• Report Number(s): CONF-780316-4
• Country of Publication: United States
• Language: English

Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
052002* -- Nuclear Fuels-- Waste Disposal & Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
Boiling-Water Reactor (BWR)
Ceramic Pellets
ENERGY SOURCES
FEASIBILITY STUDIES
FORECASTING
FUEL ASSEMBLIES
FUEL CYCLE
FUELS
Fuel Assemblies
Fuel Pins
Light Water Reactors (LWR)
MANAGEMENT
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
Pressurized-Water Reactor (PWR)
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVITY
REACTOR MATERIALS
REACTORS
SPENT FUEL STORAGE
SPENT FUELS
Spent Power Reactor Fuel
WASTE DISPOSAL
WASTE MANAGEMENT
WATER COOLED REACTORS