Fuel pin behavior of LMFBRs under severe power transients

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6983281

Struwe, D ^[1]; Papin, J ^[2]; Brear, D ^[3]; Nonaka, N ^[4]

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1. Kernforschungsanlage Juelich (Germany)
2. Commissariat a l'Energie Atomique, Saint-Paul-les-Durance (France)
3. AEA Technology, Dorset (United Kingdom)
4. Power Reactor and Nuclear Fuels Development Corp., Ibaraki-ken (Japan)

For over 15 yr, a number of experimental programs have been performed in the SURA facility in Cadarache in close cooperation between the Commissariat a l'Energie Atomique in France, Kernforschungszentrum Karlsruhe in Germany, AEA Technology in the United Kingdom, and Power Reactor and Nuclear Fuels Development Corporation in Japan, to investigate liquid-metal fast breeder reactor LMFBR fuel pin behavior up to and beyond failure. Fresh and preirradiated fuel pins have been subjected to a large variety of different flow and/or power transients. One of the aims of the CABRI-2 program was to extend the lessons learned from the CABRI-1 program to different fuel pellet types and clad materials, to different power transients, to higher burnup fuel pins, and to industrial pins with representative irradiations.

• OSTI ID: 6983281
• Report Number(s): CONF-921102--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BREEDER REACTORS
BURNUP
CABRI REACTOR
COOPERATION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
HYDRAULICS
INTERNATIONAL COOPERATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
PELLETS
POOL TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
THERMAL ANALYSIS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS