Prediction method for thermal stratification in a reactor vessel
| Autor: | Shoichi Moriya, Tomonari Koga, Yuzuru Eguchi, Satoru Ushijima, Nobukazu Tanaka |
|---|---|
| Rok vydání: | 1990 |
| Předmět: |
Nuclear and High Energy Physics
Mechanical Engineering Nuclear engineering Péclet number Nuclear reactor Plenum space law.invention Thermal hydraulics symbols.namesake Temperature gradient Breeder (animal) Nuclear Energy and Engineering law symbols Breeder reactor Environmental science General Materials Science Safety Risk Reliability and Quality Waste Management and Disposal Reactor pressure vessel |
| Zdroj: | Nuclear Engineering and Design. 120:395-402 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(90)90389-f |
| Popis: | The prediction method for thermal stratification phenomena in a fast breeder reactor is described. The focus of attention is placed on the applicability of water test results to predict thermal stratification phenomena in a real plant. The basic feature of thermal stratification was examined in a cylindrical plenum, using water and sodium as test fluids. The similitude relationship between a small-scale test and a real plant is discussed in order to understand the experimental results. The scale-model experiments for LMFBRs (liquid metal-cooled fast breeder reactors) were also performed to see the effects of a reactor configuration and reactor-trip operation condition. Then the magnitudes of the temperature gradient and the ascending speed of stratified interface in the hot plenum of LMFBRs were predicted, based on the results of the water scale-model. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|