Published February 15, 1975 | Version v1
Report Restricted

Reprocessing development for HTGR fuels

Creators

Description

The technology required for the recycle of the bred 233U in the HTGR fuel requires reprocessing to extract the valuable fissile materials in the spent fuel from the fission product wastes and refabrication. The development program being undertaken for reprocessing of HTGR fuels is described. Reprocessing flowsheet, process requirements, size reduction, fluidized-bed burning, dissolution, solvent extraction, and waste disposal are considered. (U.S.)

Availability note (English)

MF available from INIS under the Report Number.

Files

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Additional details

Publishing Information

Imprint Pagination
38 p.
Report number
GA-A--13279

Conference

Title
American Nuclear Society meeting on commercial nuclear fuel technology today.
Dates
27 Apr 1975.
Place
Toronto, Ontario, Canada.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
6204047
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DISSOLUTION; FABRICATION; FISSION PRODUCTS; FLUIDIZED BED; FUEL CYCLE; HTGR TYPE REACTORS; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTES; REPROCESSING; SOLVENT EXTRACTION; SPENT FUEL ELEMENTS; URANIUM 233
Descriptors DEC
ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-ODD NUCLEI; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY NUCLEI; ISOTOPES; MANAGEMENT; NUCLEI; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SEPARATION PROCESSES; URANIUM ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; YEARS LIVING RADIOISOTOPES

Optional Information

Secondary number(s)
CONF-750424--2.