Development of a plutonium-239 recovery incinerator
Conference
·
OSTI ID:5497957
A Plutonium-239 Recovery Incinerator is being developed for the Savannah River Plant (SRP) to reduce the volume of solid glovebox waste and to allow recovery of Pu-239 from the waste. The process will also allow treatment of some waste materials that are not certifiable for disposal at the Waste Isolation Pilot Plant (WIPP). It will consist of two electrically heated combustion chambers (furnace and afterburner) and a dry filtration off-gas system. A unique feature of the process is that it uses pyrohydrolysis to produce an ash that is amenable to Pu recovery through nitric acid/HF dissolution. A series of thermogravimetric (TGA) analyses have been performed to characterize potential incinerator feed materials. A functioning furnace mockup was built and operated to demonstrate electrically-heated pyrohydrolysis operation. 8 refs., 4 figs.
- Research Organization:
- Savannah River Lab., Aiken, SC (USA)
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 5497957
- Report Number(s):
- DP-MS-87-120; CONF-880201-18; ON: DE88006662
- Country of Publication:
- United States
- Language:
- English
Similar Records
Plutonium-239 Recovery Incinerator: Technical data summary
Conceptual design of a small-scale plutonium recovery incinerator
Systematic evaluation of options to avoid generation of noncertifiable transuranic (TRU) waste at Los Alamos National Laboratory
Technical Report
·
Tue Mar 31 23:00:00 EST 1987
·
OSTI ID:6972990
Conceptual design of a small-scale plutonium recovery incinerator
Technical Report
·
Mon Aug 25 00:00:00 EDT 1986
·
OSTI ID:7153950
Systematic evaluation of options to avoid generation of noncertifiable transuranic (TRU) waste at Los Alamos National Laboratory
Conference
·
Sat Feb 28 23:00:00 EST 1998
·
OSTI ID:642813
Related Subjects
052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CHEMICAL REACTIONS
COMBUSTION
DATA
DATA PROCESSING
DESIGN
DIAGRAMS
EVEN-ODD NUCLEI
EXPERIMENTAL DATA
FLOWSHEETS
HEAVY NUCLEI
INFORMATION
ISOTOPES
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEI
NUMERICAL DATA
OFF-GAS SYSTEMS
OXIDATION
PERFORMANCE TESTING
PLUTONIUM 239
PLUTONIUM ISOTOPES
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOISOTOPES
RECOVERY
REDUCTION
SAVANNAH RIVER PLANT
TASK SCHEDULING
TESTING
THERMOCHEMICAL PROCESSES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VOLUME
WASTE DISPOSAL
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
YEARS LIVING RADIOISOTOPES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CHEMICAL REACTIONS
COMBUSTION
DATA
DATA PROCESSING
DESIGN
DIAGRAMS
EVEN-ODD NUCLEI
EXPERIMENTAL DATA
FLOWSHEETS
HEAVY NUCLEI
INFORMATION
ISOTOPES
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEI
NUMERICAL DATA
OFF-GAS SYSTEMS
OXIDATION
PERFORMANCE TESTING
PLUTONIUM 239
PLUTONIUM ISOTOPES
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOISOTOPES
RECOVERY
REDUCTION
SAVANNAH RIVER PLANT
TASK SCHEDULING
TESTING
THERMOCHEMICAL PROCESSES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VOLUME
WASTE DISPOSAL
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
YEARS LIVING RADIOISOTOPES