Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes
- Lappeenranta Univ. of Technology, Lappeenranta (Finland)
- VTT Energy, Nuclear Energy, Lappeenranta (Finland)
Three experiments were conducted to study the behavior 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 to that the results may be compared. Only the steam generator was modelled 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.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Kyoto (Japan)
- OSTI ID:
- 111433
- Report Number(s):
- NUREG/CP--0142-Vol.4; CONF-950904--Vol.4; ON: TI95017080
- Country of Publication:
- United States
- Language:
- English
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