Gas-cooled fast breeder reactor fuel bundle irradiations in the BR2 helium loop
Description
In the BR2 helium loop at Mol, Belgium, a 12-pin test fuel element of gas-cooled fast breeder reactor (GCFR) design and materials will be irradiated at a 500 W/cm maximum pin rating and a 7000C maximum cladding temperature to a target burnup of 60 MWd/kg (extension to 100 MWd/kg is intended). The design of the test element and the loop is described in detail. To fabricate the test element, parts of the GCFR fuel development had to be anticipated. Preliminary out-of-pile testing was successfully performed, and irradiation is scheduled to start in early 1977 and will be completed between mid-1978 and mid-1979, depending on the final burnup objective. GCFR operating conditions will be completely simulated except for the full size of the fuel element and the fast neutron flux. In combination with out-of-pile performance testing of full-size dummy elements and fast flux experience from the liquid metal fast breeder reactor program, the helium loop irradiation is regarded as an adequate basis for the design of a fuel element for a GCFR demonstration plant serving as the final test bed. (Auth.)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 40
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 157-170
- ISSN
- 0029-5493
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8311032
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BR-02 REACTOR; BURNUP; FAST NEUTRONS; FUEL ELEMENT CLUSTERS; FUEL PINS; GCFR REACTOR; IRRADIATION; NEUTRON FLUX
- Descriptors DEC
- BARYONS; BERYLLIUM MODERATED REACTORS; BREEDER REACTORS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; FUEL ASSEMBLIES; FUEL ELEMENTS; GAS COOLED REACTORS; HADRONS; METAL MODERATED REACTORS; NEUTRONS; NUCLEONS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent