Published 2007 | Version v1
Book

From the acquisition of basic data to the processes for the treatment of spent fuels

  • 1. CEA Marcoule 30 (France)
  • 2. CIEMAT Madrid (Spain)
  • 3. Electricite de France (EDF), 75 - Paris (France)
  • 4. Ente per le Nuove tecnologie, l'Energia e l'Ambiente - ENEA (Italy)
  • 5. European Commission - DG Joint Research Centre - Institute for TransUranium elements - ITU EC-JRC (Germany)
  • 6. NEXIA Solutions (United Kingdom)
  • 7. Nuclear Research Institute - NRI (Czech Republic)
  • 8. Central Research Institute of Electric Power Industry - CRIEPI (Japan)
  • 9. Australian Nuclear Science and Technology Organisation - ANSTO (Australia)

Description

In the continuation of PYROREP (FP5), the pyrochemical domain of EUROPART (FP6) involves today seven European participants and two international partners in order to assess treatment processes which could be used in a broad variety of fuel cycles (MSR spent fuel, metallic, oxide, carbide or nitride fuels from any reactors). Indeed, a pyrochemical process is not sensitive to radiolysis, and obviously to temperature effects, and could afford to treat fuels after a short cooling period, even at high concentrations. Within EUROPART, the chemistry of actinides and of some fission products was studied in depth in either chloride or fluoride molten salts. Laboratory-scale demonstration experiments were used in order to assess electrolytic processes in molten chlorides and liquid-liquid reductive extraction in molten fluoride/liquid aluminium. An electrolysis process is also under development in molten fluoride. To complete the studies, the development of devices and the modelling of processes are taken into consideration. In order to be fitted for acceptance, a process has to produce minimal quantities of wastes, compatible with storage constraints. Therefore, decontamination techniques, as well as materials suitable for disposal, have to be developed. Fission products precipitation by carbonate and phosphate, and filtration on zeolites were studied. Some original confinement matrices such as sodalite or pollucite were also studied. Integration studies have been carried out in order to evaluate and to compare some selected process flow sheets and possibly to redirect R and D programmes. (authors)

Part of:
Actinide and fission product partitioning and transmutation

Additional details

Publishing Information

Publisher
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
Imprint Place
Paris (France)
ISBN
92-64-99030-2
Imprint Title
Actinide and fission product partitioning and transmutation
Imprint Pagination
750 p.
Journal Page Range
p. 207-217

Conference

Title
9. information exchange meeting
Dates
25-29 Sep 2006
Place
Nimes (France)

INIS

Country of Publication
France
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
39088753
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLOWSHEETS; FUEL CYCLE; PYROCHEMICAL REPROCESSING; RADIOACTIVE WASTE MANAGEMENT; SIMULATION; SPENT FUELS
Descriptors DEC
DIAGRAMS; ENERGY SOURCES; FUELS; INFORMATION; MANAGEMENT; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REPROCESSING; SEPARATION PROCESSES; WASTE MANAGEMENT

Optional Information