STATISTICAL METHODS FOR HOT CHANNEL AND HOT SPOT CALCULATION. Quarterly Progress Report No. 3, July 1, 1961 to September 30, 1961
Technical Report
·
OSTI ID:4818813
A model was developed to take into account the statistical deviations of design parameters from their nominal value. In this model, the reactor core (or a channel of it) is divided in a certain number of small regions ( spots''); in each of them every independent design parameter such as fuel density and enrichment and geometric dimensions being characterized by a fixed statistical distribution around the nominal value. A condition was introduced in which every parameter in a certain region is statistically independent from the values of all other parameters in all other core (or channel) regions. Owing to the simplicity of this model, it will be applied to the determination of the probability function of all the dependent variable interesting a nuclear-thermal-hydraulic core design. Formula were set up, uslng a linearization procedure, for the distribution and probability function of parameters such as enthalpy and bulk temperature, quality and void fraction, points of inception of local and bulk boiling, and various partial pressure drops in heating, local and bulk boiling regimes. From a statistical intersectlon of the total pressure drop curve versus total mass flow rate in the core with the entire system pressure drop-flow characteristic curve, the distribution of the mass rate of flow and pressure drops in every channels could be found. An analytical procedure is being developed which can be use to find the probability functions of maximum'' type parameters (for example: maximum surface temperature, maximum meat centerline temperature, maximum heat velocity or "burnout" flux). (auth)
- Research Organization:
- FIAT. Sezione Energia Nucleare, Turin
- NSA Number:
- NSA-16-018616
- OSTI ID:
- 4818813
- Report Number(s):
- EURAEC-191; FN-E-12
- Country of Publication:
- United States
- Language:
- English
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