Analytical and experimental investigation of the dispersion process during rapid transients for the aluminum-based nuclear fuel plates
- 1. Oak Ridge National Lab., TN (United States)
- 2. Japan Atomic Energy Research Inst., Takai, Ibaraki (Japan)
Description
A thermally induced fuel-plate dispersion model was developed to analyze for dispersive potential and determine the onset of fuel plate dispersion for aluminum-based research and test reactor fuels. The effect of rapid energy deposition in a fuel plate was simulated. Several data types for aluminum-based fuels tested in the Nuclear Safety Research Reactor (NSRR) facility in Japan and in the Transient Reactor Test (TREAT) facility in Idaho, US, were reviewed. Analyses of experiments show that the onset of fuel dispersion is clearly linked to a sharp rise in the predicted strain rate, which further coincides with the onset of aluminum vaporization. Analysis also shows that aluminum oxidation and exothermal chemical reaction between the fuel and aluminum can significantly affect: the energy deposition characteristics and, therefore dispersion onset connected with aluminum vaporization, and the onset of aluminum vaporization
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE96003190; NTIS; US Govt. Printing Office Dep.Files
27036743.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 118 p.
- Report number
- ORNL/TM--12956
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27036743
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ANALYTICAL SOLUTION; EVAPORATION; EXPERIMENTAL DATA; FUEL PLATES; FUEL-CLADDING INTERACTIONS; FUEL-COOLANT INTERACTIONS; MASS TRANSFER; MATHEMATICAL MODELS; NSRR REACTOR; PARAMETRIC ANALYSIS; REACTOR ACCIDENTS; RESEARCH AND TEST REACTORS; THEORETICAL DATA; TREAT REACTOR
- Descriptors DEC
- ACCIDENTS; AIR COOLED REACTORS; DATA; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INFORMATION; MIXED SPECTRUM REACTORS; NUMERICAL DATA; PHASE TRANSFORMATIONS; PULSED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- USDOE, Washington, DC (United States).