Plutonium-239 Recovery Incinerator: Technical data summary

Technical Report · Wed Apr 01 04:00:00 EST 1987

OSTI ID:6972990

Williams, S

FB-Line generates an average of 1300 ft/sup 3/ of combustible cabinet waste per year, which contain up to 30 kg of Pu-239. Also generated is waste that is not certifiable for shipment to the Waste Isolation Pilot Plant (WIPP). Phase IV of FB-Line Productivity Retention Project will install a waste handling facility to process combustible and noncombustible waste. The Plutonium-239 Recovery Incinerator (PRI) is being designed to process the high activity fraction of the combustible waste. Also, it will be able to incinerate at least part of the non-certifiable waste. The PRI will burn waste in a steam atmosphere, which allows combustion at temperatures less than 700/degree/C to produce dissoluble ash amenable to Pu recovery by dissolution. 6 refs., 8 figs., 3 tabs.

• Research Organization: Savannah River Lab., Aiken, SC (USA)
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 6972990
• Report Number(s): DPSTD-87-3-Rev.1; ON: DE89000018
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
AEROSOL WASTES
ALPHA DECAY RADIOISOTOPES
ASHES
CHEMICAL REACTIONS
COMBUSTION
DESIGN
EVALUATION
EVEN-ODD NUCLEI
FLY ASH
HEAVY NUCLEI
INCINERATORS
ISOTOPES
MATERIALS
NUCLEAR FACILITIES
NUCLEI
OFF-GAS SYSTEMS
OPERATION
OXIDATION
PLUTONIUM 239
PLUTONIUM ISOTOPES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
RADIOISOTOPES
RESIDUES
SAFETY
THERMOCHEMICAL PROCESSES
WASTES
YEARS LIVING RADIOISOTOPES