Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes
| Autor: | E. Virtanen, Timo Haapalehto, Jyrki Kouhia |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 1997 |
| Předmět: |
Nuclear and High Energy Physics
Engineering Computer simulation Hydraulics business.industry Mechanical Engineering Nuclear engineering Boiler (power generation) Boiler feedwater Mechanical engineering food and beverages Nuclear reactor complex mixtures law.invention Coolant Thermal hydraulics Nuclear Energy and Engineering law Heat exchanger General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal |
| Zdroj: | Virtanen, E, Haapalehto, T & Kouhia, J 1997, ' Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes ', Nuclear Engineering and Design, vol. 177, no. 1-3, pp. 147-153 . https://doi.org/10.1016/S0029-5493(97)00191-X |
| DOI: | 10.1016/S0029-5493(97)00191-X |
| Popis: | Three experiments were conducted to study the behaviour of the new horizontal steam generator construction of the PACTEL test facility. In the experiments the secondary side coolant level was reduced stepwise. The experiments were calculated with two computer codes RELAP5/MOD3.1 and APROS version 2.11. A similar nodalization scheme was used for both codes so that the results may be compared. Only the steam generator was modeled and the rest of the facility was given as a boundary condition. The results show that both codes calculate well the behaviour of the primary side of the steam generator. On the secondary side both codes calculate lower steam temperatures in the upper part of the heat exchange tube bundle than was measured in the experiments. |
| Databáze: | OpenAIRE |
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