Oxalate process: the unique way for plutonium conversion
Creators
- 1. SGN 1 rue des Herons 78182 Montigny le Bretonneux (France)
- 2. Cogema, 2 rue Paul Dautier, 78140 Velizy-Villacoublay (France)
Description
The continuous oxalate process has been selected from the very beginning of industrial reprocessing. Oxalate conversion process is described as well as the various facilities where this process has been implemented. It demonstrates the unique experience gained by COGEMA in this field, in terms of high throughput, total volume of production, quality of product and safety of operation. Numerous improvements have been brought to the process, among which the most important are: - the process qualification, which allows to ensure a constant quality of final product, - the degree of automation aimed at decreasing and even deleting any manual operation, - the safety and criticality principles such as the extensive use of geometrically safe equipment, the full implementation of double containment, - the increase of throughput, to comply with the requirement of large modem reprocessing plants, This continuous progress has been possible thanks to a vigorous R and D. The large experience gained today in mixed oxide fuel (MOX) fabrication demonstrates that oxalate process is fully qualified to ensure the complete closure of fuel cycle. The oxalate continuous conversion process will be soon applied in the field of recovery of weapons grade plutonium
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- Jackson Hole, Wyoming (United States)
- Imprint Pagination
- 6 p.
Conference
- Title
- International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
- Acronym
- Global'99
- Dates
- 29 Aug - 3 Sep 1999
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53059351
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUTOMATION; CRITICALITY; FUEL CYCLE; FUEL REPROCESSING PLANTS; IMPLEMENTATION; MIXED OXIDE FUELS; OPERATION; OXALATES; PLUTONIUM; REPROCESSING
- Descriptors DEC
- ACTINIDES; CARBOXYLIC ACID SALTS; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; NUCLEAR FACILITIES; NUCLEAR FUELS; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 3 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)