• Title/Summary/Keyword: safety relief valve

Search Result 52, Processing Time 0.049 seconds

Waterhammer for the Intake Pumping Station with the Pump Control Valve (펌프제어밸브를 사용한 취수펌프장에서의 수격현상)

  • Kim, Kyung-Yup;Oh, Sang-Hyun
    • The KSFM Journal of Fluid Machinery
    • /
    • v.4 no.4 s.13
    • /
    • pp.16-21
    • /
    • 2001
  • The field tests on the waterhammer were carried out for PalDang intake pumping station of the metropolitan water supply 5th stage project. The pumping station was equipped with the pump control valve as the main surge suppression device and the surge relief valve as auxiliary. However, the pump control valve had not been early controlled in the planned closing mode, and the slamming occurred to the valve which abruptly closed during the large reverse flow. Because the pressure wave caused by the pump failure was superposed on the slam surge, the upsurge increased so extremely that the shaft of the valve was damaged. It was desirable that the surge relief valve was installed in the pumping station or near the pump exit for the delay of response. After reforming the oil dashpot of the pump control valve, the sliming disappeared and the measured pressure was in fairly good agreement with the results of simulation. In case of three pumps for ${\phi}2,600$ pipeline being simultaneously tripped, the pressure head in the pumping station increased to 95.6 m, and the upsurge caused by the emergency stop of four pumps for ${\phi}2,800$ pipeline was 89.6m. We concluded that the pumping station acquired the safety and reliability for the pressure surge.

  • PDF

Pressure Wave Propagation in the Discharge Piping with Water Pool

  • Bang Young S.;Seul Kwang W.;Kim In-Goo
    • Nuclear Engineering and Technology
    • /
    • v.36 no.4
    • /
    • pp.285-294
    • /
    • 2004
  • Pressure wave propagation in the discharge piping with a sparger submerged in a water pool, following the opening of a safety relief valve, is analyzed. To predict the pressure transient behavior, a RELAP5/MOD3 code is used. The applicability of the RELAP5 code and the adequacy of the present modeling scheme are confirmed by simulating the applicable experiment on a water hammer with voiding. As a base case, the modeling scheme was used to calculate the wave propagation inside a vertical pipe with sparger holes and submerged within a water pool. In addition, the effects on wave propagation of geometric factors, such as the loss coefficient, the pipe configuration, and the subdivision of sparger pipe, are investigated. The effects of inflow conditions, such as water slug inflow and the slow opening of a safety relief valve are also examined.

Analysis of Dynamic Characteristics and Performances of Vent-Relief Valve (산화제 벤트/릴리프밸브의 동특성 해석 및 작동성능분석)

  • Jang, Je-Sun;Koh, Hyeon-Seok;Han, Sang-Yeop;Lee, Kyung-Won
    • Proceedings of the Korean Society of Propulsion Engineers Conference
    • /
    • 2010.11a
    • /
    • pp.741-747
    • /
    • 2010
  • Vent-relief valve performed as a safety-valve combination for liquid propellant feeding system of space launch vehicle, which can vent the vaporized oxygen vapor during both filling cryogenic oxidizer into tank and flight. We have designed vent-relief model by using the AMESim code to predict dynamic characteristics and simulate pneumatic behavior of valve. To validate valve model we have compared by opening time in vent model, and opening/closing pressure by mathematical methods and improved the accuracy through numerical flow analysis by using FLUENT code. In this study, we had verified design parameters and analyzed operating performances. We can use these analysis results to precedent development study on propellant feeding system of Korea Space Launch Vehicle.

  • PDF

Sealing design optimization of nuclear pressure relief valves based on the polynomial chaos expansion surrogate model

  • Chaoyong Zong;Maolin Shi;Qingye Li;Tianhang Xue;Xueguan Song;Xiaofeng Li;Dianjing Chen
    • Nuclear Engineering and Technology
    • /
    • v.55 no.4
    • /
    • pp.1382-1399
    • /
    • 2023
  • Pressure relief valve (PRV) is one of the important control valves used in nuclear power plants, and its sealing performance is crucial to ensure the safety and function of the entire pressure system. For the sealing performance improving purpose, an explicit function that accounts for all design parameters and can accurately describe the relationship between the multi-design parameters and the seal performance is essential, which is also the challenge of the valve seal design and/or optimization work. On this basis, a surrogate model-based design optimization is carried out in this paper. To obtain the basic data required by the surrogate model, both the Finite Element Model (FEM) and the Computational Fluid Dynamics (CFD) based numerical models were successively established, and thereby both the contact stresses of valve static sealing and dynamic impact (between valve disk and nozzle) could be predicted. With these basic data, the polynomial chaos expansion (PCE) surrogate model which can not only be used for inputs-outputs relationship construction, but also produce the sensitivity of different design parameters were developed. Based on the PCE surrogate model, a new design scheme was obtained after optimization, in which the valve sealing stress is increased by 24.42% while keeping the maximum impact stress lower than 90% of the material allowable stress. The result confirms the ability and feasibility of the method proposed in this paper, and should also be suitable for performance design optimizations of control valves with similar structures.

Case Study of Repair Works on Surge Suppression Device for Booster Pumping Station (가압펌프장의 수격완화설비에 대한 보수·보강 사례)

  • Kim, Sang-gyun;Lee, Dong-keun;Lee, Gye-bok;Kim, Kyung-yup
    • The KSFM Journal of Fluid Machinery
    • /
    • v.8 no.4 s.31
    • /
    • pp.20-26
    • /
    • 2005
  • When the pumps are started or stopped for the operation or tripped due to the power failure, the hydraulic transients occur as a result of the sudden change in velocity. The field tests on the waterhammer were carried out for Pangyo booster pumping station in which had six booster pumps and two in-line pumps with the motor of output 1,700 kW, respectively. The booster pumping station was equipped with the pump control valve as the main surge suppression device, and the surge relief valve as auxiliary one. But the pump control valve had not early controlled in the planned closing mode, the slamming occurred to the valve of which abruptly closed during the large reverse flow. Because the positive pressure wave caused by the pump failure was superposed on the slam surge, the upsurge increased so extremely that the pump control valve was damaged. After the air chambers were additionally installed in the booster pumping station, it was preyed that the water supply system acquire the safety and reliability on the pressure surge.

Simulation of Multiple Steam Generator Tube Rupture (SGTR) Event Scenario

  • Seul Kwang Won;Bang Young Seok;Kim In Goo;Yonomoto Taisuke;Anoda Yoshinari
    • Nuclear Engineering and Technology
    • /
    • v.35 no.3
    • /
    • pp.179-190
    • /
    • 2003
  • The multiple steam generator tube rupture (SGTR) event scenario with available safety systems was experimentally and analytically evaluated. The experiment was conducted on the large scaled test facility to simulate the multiple SGTR event and investigate the effectiveness of operator actions. As a result, it indicated that the opening of pressurizer power operated relief valve was significantly effective in quickly terminating the primary-to-secondary break flow even for the 6.5 tubes rupture. In the analysis, the recent version of RELAP5 code was assessed with the test data. It indicated that the calculations agreed well with the measured data and that the plant responses such as the water level and relief valve cycling in the damaged steam generator were reasonably predicted. Finally, sensitivity study on the number of ruptured tubes up to 10 tubes was performed to investigate the coolant release into atmosphere. It indicated that the integrated steam mass released was not significantly varied with the number of ruptured tubes although the damaged steam generator was overfilled for more than 3 tubes rupture. These findings are expected to provide useful information in understanding and evaluating the plant ability to mitigate the consequence of multiple SGTR event.