Published February 1976
| Version v1
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Calculational methods for power capability studies
Description
A formulation is developed to study reactor power capability based on the likelihood of incipient centerline fuel melting. Attention is also directed to the proper definition of this likelihood. As a consequence, it is shown how to compute the total probability for fuel melting as well as the expected number of fuel pellets and the associated variance. Factors considered include statistical variations in pellet fissile densities, gap sizes, coolant temperatures, reactor power, and the power-to-melt function. General formulas suitable for computation are given along with more transparent analytical results
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS.
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Additional details
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- HEDL-TME--75-141
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7265876
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- EQUATIONS; FUEL ELEMENTS; FUEL PELLETS; MELTING; PLUTONIUM DIOXIDE; POWER DENSITY; PROBABILITY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR COMPONENTS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Available from NTIS. $5.00.