Published 1987 | Version v1
Book Metadata-only

The solubility of fast reactor fuel during reprocessing

Creators

  • 1. UKAEA Windscale Nuclear Lab.
  • 2. UKAEA Dounreay Nuclear Lab.
  • 3. UKAEA Harwell Lab.

Description

To minimize plutonium losses in the fast reactor fuel cycle it is essential that during reprocessing the UPu oxide fuel is soluble in the nitric acid solvent used in the reprocessing plant. In the UK an attempt is being made to quantify the amount of plutonium which might be contained in insoluble fuel residues. This paper provides an account of work being carried out on unirradiated and irradiated fuel in the UK on the solubility of UPu oxide fuel

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire.
Imprint Place
Paris (France)
Imprint Title
RECOD 87
Imprint Pagination
479 p.
Journal Page Range
p. 577-581.

Conference

Title
International Conference on Nuclear Fuel Reprocessing and Waste Management.
Dates
23-27 Aug 1987.
Place
Paris (France).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
19091841
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; CHEMICAL DECLADDING; MIXING; PFR REACTOR; SINTERING; SOLUBILITY; SPENT FUEL ELEMENTS; TEMPERATURE DEPENDENCE
Descriptors DEC
BREEDER REACTORS; DECLADDING; EPITHERMAL REACTORS; FABRICATION; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; HEAD END PROCESSES; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS