Subchannel analysis of a critical power test, using simulated BWR S × S fuel assembly
| Autor: | Mamoru Akiyama, H. Terasaka, Kunihiro Yoshimura, Akira Inoue, Toru Mitsutake, M. Oishi |
|---|---|
| Rok vydání: | 1990 |
| Předmět: |
Nuclear and High Energy Physics
Engineering Source code Critical heat flux business.industry Mechanical Engineering media_common.quotation_subject Nuclear engineering Structural engineering Liquid film Nuclear Energy and Engineering Critical power General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal media_common Test data |
| Zdroj: | Nuclear Engineering and Design. 122:235-254 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(90)90209-g |
| Popis: | Critical power predictions have been compared with the critical power test data obtained in simulated BWR 8 × 8 fuel rod assemblies. Two analytical methods for the critical power prediction in rod assemblies are used in the prediction, which are the subchannel analysis using the COBRA/BWR subchannel computer code with empirical critical heat flux (CHF) correlations and the liquid film dryout estimation using the CRIPP-3F ‘multi-fluid’ computer code. Improvements in both the analytical methods were made for spacer effect modeling, though they were specific for application to the current BWR rod assembly type. In general a reasonable agreement was obtained, through comparisons, between the prediction and the obtained test data. |
| Databáze: | OpenAIRE |
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