Highly irradiated fuel behavior up to melting: JOG tests in CABRI
Creators
- 1. Commissariat a l'Energie Atomique, Saint-Paul-les-Durance (France)
- 2. Kernforschungszentrum Karlsruhe (Germany)
- 3. United Kingdom Atomic Energy Authority, Warrington (United Kingdom)
Description
In the study of fuel pin behavior at high burnup, the fuel temperatures during steady state and the power to melt are not known with sufficient precision. This is partly due to the existence and growth of a layer of fission product compounds called joint oxide gain (JOG), which means oxide-cladding joint, at the fuel-clad interface. The physical properties of this JOG layer, especially its thermal conductivity, are difficult to measure out of pile. A program of in-pile experiments, called JOG tests, has therefore been developed. One test has been carried out. This program consists of two tests performed in the Cabri reactor at Cadarache, Each test simulates a control rod withdrawal (power ramp of 1% nominal power per second) stopped at a power sufficient to provoke fuel melting but lower than that required to fail the pin
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 207.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24050973
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CABRI REACTOR; FISSION PRODUCTS; FUEL CANS; FUEL ELEMENT FAILURE; FUEL PINS; FUEL-CLADDING INTERACTIONS; IRRADIATION; MELTING; OXIDES; PERFORMANCE TESTING; ROD EJECTION ACCIDENTS; SIMULATION; THERMAL CONDUCTIVITY
- Descriptors DEC
- ACCIDENTS; CHALCOGENIDES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; ISOTOPES; MATERIALS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-921102--.