MELCOR Modeling of the National Research Universal Full-Length High-Temperature 2 Experiment
| Autor: | I.K. Madni, Xiao-Dong Guo |
|---|---|
| Rok vydání: | 1992 |
| Předmět: |
Nuclear and High Energy Physics
Computer simulation 020209 energy Nuclear engineering Pressurized water reactor Experimental data 02 engineering and technology Nuclear reactor Condensed Matter Physics law.invention 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering law MELCOR Bundle Heat transfer 0202 electrical engineering electronic engineering information engineering Environmental science Test data Nuclear chemistry |
| Zdroj: | Nuclear Technology. 99:203-212 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt92-a34690 |
| Popis: | The MELCOR computer code has been used to simulate the National Research Universal full-length high-temperature 2 (FLHT-2) test. Input data for the analysis were obtained from the FLHT-2 test Data Report and from SCDAP input. In this paper results are presented for the transient liquid level in the test bundle, heat transfer to the bypass flow, cladding and shroud temperatures, and hydrogen generation. Comparisons are made with experimental data and with SCDAP calculations. Several sensitivity calculations with MELCOR, which explore the impact of varying user-input modeling and time-step control parameters on the predicted behavior, were also carried out. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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