High-temperature methods for treating spent fuel cladding
Creators
- 1. Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow
Description
The physical and chemical characteristics of the wastes from power plant fuel claddings are presented and high-temperature methods of preparing them for long-term storage are discussed. It is shown that a promising approach is that of conducting the operations of conditioning fuel cladding waste at the initial stages of reprocessing by thermal decladding of spent fuel elements. In this way: the fuel to be reprocessed is separated to the extent of 95-99% from the cladding material; gaseous and volatile fission products are eliminated; the cladding material is moulded into compact ingots suitable for long-term storage; insignificant quantities of fuel components and fission products go into the ingot; the main activity of the ingots is determined by the 60Co, 137Cs, 90Sr, etc. isotopes; the volume of solid and gaseous wastes are minimal and no liquid wastes are produced. It is also shown that it is advantageous to re-melt non-compact claddings to form ingots after the mechanical chopping and dissolving operations. This reduces the required waste storage volume by a factor of 1.5-3 and the metal surface by a factor of 1000, so that there is a considerable decrease in the surface contamination of the materials by fission products and a reduction in the surface diffusion of isotopes and their corrosion activity
Additional details
Additional titles
- Original title (no language)
- Traitement, conditionnement et stockage des dechets solides alpha et des coques de degainage. Paris, 5-7 decembre 1977.
Publishing Information
- Publisher
- OECD.
- Imprint Place
- Paris, France
- ISBN
- 92-64-01747-X
- Imprint Title
- Treatment, conditioning and storage of solid alpha-bearing waste and cladding hulls. Paris, 5-7 December 1977
- Journal Page Range
- p. 323-336.
Conference
- Title
- NEA/IAEA technical seminar on treatment, conditioning and storage of solid alpha-bearing waste and cladding hulls.
- Dates
- 5 - 7 Dec 1977.
- Place
- Paris, France.
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 9412119
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DECLADDING; FISSION PRODUCTS; HIGH TEMPERATURE; PLUTONIUM DIOXIDE; RADIOACTIVE WASTE PROCESSING; SPENT FUELS; STAINLESS STEELS; URANIUM DIOXIDE; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; ENERGY SOURCES; FUELS; HEAD END PROCESSES; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MANAGEMENT; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; STEELS; TRANSITION ELEMENT ALLOYS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Notes
- Imprint:Traitement, conditionnement et stockage des dechets solides alpha et des coques de degainage. Paris, 5-7 decembre 1977.;Compte rendu du seminaire technique AEN/AIEA.