• Title/Summary/Keyword: Residual Heat Removal System

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A Study on the Vent Path Through the Pressurizer Manway and Steam Generator Manway under Loss of Residual Heat Removal System During Mid-loop Operation in PWR (가압경수로의 부분충수 운전중 잔열제거계통 기능 상실사고시 가압기와 증기발생기 Manway 유출유로를 이용한 사고완화에 관한 연구)

  • Y. J. Chung;Kim, W. S.;K. S. Ha;W. P. Chang;K. J. Yoo
    • Nuclear Engineering and Technology
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    • v.28 no.2
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    • pp.137-149
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    • 1996
  • The present study is to analyze an integral test, BETHSY test 6.9c, which represent loss of RURS accident under mid-loop operation. Both the pressurizer manway and the steam generator outlet plenum manway are opened as vent paths in order to prevent the system from pressurization by removing the steam generated in the core. The main purposes are to gain insights into the physical phenomena and identify sensitive parameters. Assessment of capability of CATHARE2 prediction can be established the effective recovery procedures using the code in an actual plant. Most of important physical phenomena in the experiment could be predicted by the CATHARE2 code. The peak pressure in the upper plenum is predicted higher than experimental value by 7 kPa since the differential pressure between the pressurizer and the surge line is overestimated. The timing of core uncovery is delayed by 500 seconds mainly due to discrepancy in the core void distribution. It is demonstrated that openings of the pressurizer manwey and the steam generator manway can prevent the core uncovery using only gravity feed injection. Although some disagreements are found in the detailed phenomena, the code prediction is considered reasonable for the overall system behaviors.

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Analysis of the Vent Path Through the Pressurizer Manway Under the Loss of Residual Heat Removal(RHR) System During Mid-Loop Operation in PWR (가압경수로 부분충수 운전중 잔열제거 (RHR)계통 상실시 가압기 통로를 통한 배출유로 특성 분석)

  • Ha, G.S.;Kim, W.S.;Chang, W.P.;Yoo, K.J.
    • Nuclear Engineering and Technology
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    • v.27 no.6
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    • pp.859-869
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    • 1995
  • The present study is to understand the physical phenomena anticipated during the accident with RHR loss under mid-loop operation in a PWR and, at the same time, to examine the prediction capability of RELAP5/MOD3.1 on such an accident, by simulating an integral test relevant to this accident for reliable analysis in an actual PWR. The selected experiment, i.g. BETHSY Test 6.9a, represents the configuration with the pressurizer manway open and steam generators unavailable during the accident. Accordingly, the results of this ok are sure to contribute to understanding both the key events as well as the sensitive parameters, anticipated in the accident, for validity of the actual analysis. In the simulation result overall behavior as well as major phenomena observed in the experiment have been predicted reasonably by RELAP5/MOD3.1, however, the problem associated with enormous computing time .due to small time step size has been encountered. Besides, the code prediction of higher swollen level in the pressure vessel has given rise to overestimation of both pressurizer level and RCS pressure. Subsequently, overprediction of the break flow through the manway has led to earlier core uncovery than that in the experiment by about 400 seconds. As a whole, it is demonstrated from both the experiment and the analysis that gravity feed has not been sufficient to recover the core level and thus additional forced feed has been necessary in this configuration.

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