Published 1986 | Version v1
Report Open

Plans for the development of the IFR [Integral Fast Reactor] fuel cycle

Description

The Integral Fast Reactor (IFR) is a concept for a self-contained facility in which several sodium-cooled fast reactors of moderate size are located at the same site along with complete fuel-recycle and waste-treatment facilities. After the initial core loading with enriched uranium or plutonium, only natural or depleted uranium is shipped to the plant, and only wastes in final disposal forms are shipped out. The reactors have driver and blanket fuels of uranium-plutonium-zirconium alloys in stainless steel cladding. The use of metal alloy fuels is central to the IFR concept, contributing to the inherent safety of the reactor, the ease of reprocessing, and the relatively low capital and operating costs. Discharged fuels are recovered in a pyrochemical process that consists of two basic steps: an electrolytic process to separate fission products from actinides, and halide slagging to separate plutonium from uranium

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE87004955.

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Additional details

Publishing Information

Imprint Pagination
5 p.
Report number
CONF-8610226--2

Conference

Title
6. annual plutonium pyrochemical workshop.
Dates
7-8 Oct 1986.
Place
Los Alamos, NM (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18066020
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL CYCLE; IFR REACTOR; PLUTONIUM ALLOYS; PYROCHEMICAL REPROCESSING; URANIUM ALLOYS; ZIRCONIUM ALLOYS
Descriptors DEC
ACTINIDE ALLOYS; ALLOYS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; REACTORS; REPROCESSING; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; ZERO POWER REACTORS