Experience of reprocessed uranium. Recycling in France
Creators
- 1. Cogema, 78 - Velizy-Villacoublay (France)
- 2. FRAMATOME, 92 - Paris-La-Defence (France)
Description
When discharged from nuclear reactors, irradiated fuel has, depending on the burnup, a 3 to 5% content of fission products and minor actinides, while 95 to 97% are reusable remaining uranium and created during irradiation plutonium. Recycling of valuable materials has continuously been the French strategic choice since the beginning of the nuclear program, and is relying on a mastered and powerful reprocessing industry along with an outstanding industrial experience in front end steps like conversion and fuel fabrication. The French utility EDF intends to recycle all the available quantities of reprocessed uranium. Feasibility demonstration of the involved stages were undertaken in the 80's and included demonstration plants for fuel fabrication and in reactor testing. The acquired results prove that the particular characteristics of uranium coming from spent fuels do not present unresolved technological problems. Among the required specific fuel cycle facilities for reprocessed uranium full scale recycling, some are already available in France: conversion into oxide and fuel fabrication; others (conversion into UF6 and enrichment) are currently under study. After reminding some reprocessed uranium specificities, this paper will describe the present achievements of the French policy and give an outlook on near term trends. (O.M.)
Additional details
Additional titles
- Original title (English)
- Global 1995
Publishing Information
- Publisher
- Edition ANS
- Imprint Place
- Paris (France)
- Imprint Title
- Global 1995
- Imprint Pagination
- 2032 p.
- Journal Page Range
- p. 956-963
Conference
- Title
- International conference on evaluation of emerging nuclear fuel cycle systems
- Dates
- 11-14 Sep 1995
- Place
- Versailles (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 29062162
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FRANCE; ISOTOPE SEPARATION; PLUTONIUM; RECYCLING; REPROCESSING; URANIUM; URANIUM RECYCLE
- Descriptors DEC
- ACTINIDES; DEVELOPED COUNTRIES; ELEMENTS; EUROPE; FUEL CYCLE; METALS; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WESTERN EUROPE
Optional Information
- Notes
- Imprint:Global 1995