In KNGR(Korean Next Generation Reactor), if there is a failure in RCS(Reactor Coolant System) of nuclear power plant, the compressed water of RCS becomes the superheated vapor with 15.4 Mpa and 626 K, and then the nuclear power plant is faced with severe danger. So, to avoid the danger in RCS, the s...
In KNGR(Korean Next Generation Reactor), if there is a failure in RCS(Reactor Coolant System) of nuclear power plant, the compressed water of RCS becomes the superheated vapor with 15.4 Mpa and 626 K, and then the nuclear power plant is faced with severe danger. So, to avoid the danger in RCS, the superheated vapor by the opening of the POSRV installed at the top of the high pressure vessel of the reactor is discharged into IRWST(In-containment Refueling Water Storage Tank) through the various piping units of elbow, tee. branch and so on. And, the superheated vapor discharged into an IRWST is condensed, mixed into the water in the IRWST water pool, and then lost its high energy, and finally the reactor coolant system becomes safely. The objectives of this paper are to analyze complicated flow behaviors in the various downstream piping units of POSRV by numeric and experiment methods, and to investigate the effect of POSRV opening time on the load acting on the wall of the each piping unit. In the case of instant opening POSRV, the propagation of a shock wave and the load acting on the wall of piping unit related with the propagation of shock wave are calculated through the commercial code(FLUENT6) and are compared with the experimental results. After the confirming of validation of numerical analysis method which possible to obtain from the comparison between numerical and experimental results. At first, we make use of numerical method to calculate for the case of an instant opening of POSRV at T-junction. Next, to cope with the case of gradual opening of POSRV, of course whose opening time may affect the load acting on the wall of POSRV piping unit, a flow in tee is performed as model case. And, it was turned out that the larger the valve opening time is, the load acting on wall of piping unit is smaller.
In KNGR(Korean Next Generation Reactor), if there is a failure in RCS(Reactor Coolant System) of nuclear power plant, the compressed water of RCS becomes the superheated vapor with 15.4 Mpa and 626 K, and then the nuclear power plant is faced with severe danger. So, to avoid the danger in RCS, the superheated vapor by the opening of the POSRV installed at the top of the high pressure vessel of the reactor is discharged into IRWST(In-containment Refueling Water Storage Tank) through the various piping units of elbow, tee. branch and so on. And, the superheated vapor discharged into an IRWST is condensed, mixed into the water in the IRWST water pool, and then lost its high energy, and finally the reactor coolant system becomes safely. The objectives of this paper are to analyze complicated flow behaviors in the various downstream piping units of POSRV by numeric and experiment methods, and to investigate the effect of POSRV opening time on the load acting on the wall of the each piping unit. In the case of instant opening POSRV, the propagation of a shock wave and the load acting on the wall of piping unit related with the propagation of shock wave are calculated through the commercial code(FLUENT6) and are compared with the experimental results. After the confirming of validation of numerical analysis method which possible to obtain from the comparison between numerical and experimental results. At first, we make use of numerical method to calculate for the case of an instant opening of POSRV at T-junction. Next, to cope with the case of gradual opening of POSRV, of course whose opening time may affect the load acting on the wall of POSRV piping unit, a flow in tee is performed as model case. And, it was turned out that the larger the valve opening time is, the load acting on wall of piping unit is smaller.
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