Summary and analysis of treat sodium loop experiments on behavior of single EBR-II Mark I pins under accident conditions
| Autor: | F.L. Willis, L.E. Robinson, W. Stephany, C.E. Dickerman, R.T. Purviance |
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| Rok vydání: | 1968 |
| Předmět: |
Nuclear and High Energy Physics
Engineering Waste management business.industry Mechanical Engineering Nuclear engineering Flow (psychology) Power level Power (physics) Coolant Loop (topology) Nuclear Energy and Engineering Nuclear reactor core Mockup General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal Reactor safety |
| Zdroj: | Nuclear Engineering and Design. 7:442-454 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(68)90082-4 |
| Popis: | The study of fast reactor safety is concerned with a number of areas, among which the possibility of core meltdown is of major interest. A number of factors might be involved in such an accident; this article deals with a study, experimentally and by computation, of the mechanisms of fuel failure and associated movement of fuel and coolant. These two phenomena could lead to extension of any initial fuel failure and thus would probably be the factors responsible for a serious meltdown accident. Fuel failure experiments have been conducted in instrumented sodium loops, which, when installed in the TREAT reactor, provide a simulated reactor environment. These loops provide for setting conditions of varying temperature and flow of sodium coolant past the fuel elements under test; and the power burst of the TREAT reactor, into which the loops are inserted for testing, can be adjusted to specified intensities. The results of testing a number of sample fuel elements under various conditions of power level and coolant flow are presented and analyzed here. |
| Databáze: | OpenAIRE |
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