Process facility modifications project
Description
The Process Facility Modification Project (PFM) is a US Department of Energy (DOE) project which is designed to replace the existing head-end of the Plutonium Uranium Extraction (PUREX) Plant at the DOE's Hanford, Washington facilities. The purpose and need for the PFM project are twofold. First, it is desired to recover the plutonium loaned to the DOE's breeder reactor research program by the DOE's Defense Program. This plutonium is being used as fuel in the Fast Flux Test Facility (FFTF) at Hanford, Washington. The fuel consists of a mixture of PuO/UO clad in stainless steel tubes. There are presently no US facilities which can reprocess stainless-steel-clad fuel. Therefore, to recover this plutonium a new facility which uses a chop/leach process must be constructed. Secondly, it is desired to use more modern reprocessing techniques to reduce the volume of high-level liquid radioactive waste produce by PUREX. By replacing the current Zirflex headed with the chop/leach process, the amount of liquid waste generated when reprocessing N Reactor fuel can be reduced by ∼90%
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 53
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 159-160
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society and Atomic Industrial Forum joint meeting.
- Dates
- 16-21 Nov 1986.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18045044
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DECONTAMINATION; FFTF REACTOR; FUEL CANS; HANFORD ENGINEERING DEVELOPMEN; HIGH-LEVEL RADIOACTIVE WASTES; LEACHING; LIQUID WASTES; MODIFICATIONS; PLUTONIUM OXIDES; PUREX PROCESS; RADIATION PROTECTION; RADIOACTIVE WASTES; RESEARCH PROGRAMS; SAFETY; SPECIFICATIONS; SPENT FUEL ELEMENTS; STORAGE; URANIUM NITRATES; URANIUM OXIDES; US DOE; VOLUME
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CLEANING; DISSOLUTION; EPITHERMAL REACTORS; FAST REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; NITRATES; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; REPROCESSING; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; US ORGANIZATIONS; WASTES
Optional Information
- Secondary number(s)
- CONF-861102--.