• Title/Summary/Keyword: Gas-steam Ejection

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Effect of Heat Transfer and Phase Change of Coolant on the Performance of Mixed-gas Ejection System (냉각제의 분사조건 및 상변화가 혼합가스 사출시스템의 성능에 미치는 영향)

  • Kim, Hyun Muk;Kim, Jeong Soo
    • Journal of the Korean Society of Propulsion Engineers
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    • v.22 no.6
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    • pp.84-93
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    • 2018
  • Three-dimensional (3D) numerical simulations have been carried out to study how coolant injection conditions influence the cooling efficiency and projectile ejection performance in a mixture-gas ejection system (or gas-steam launch system). The 3D single-phase computational model was verified using a 1D model constructed with reference to the previous research and then a two-phase flow computation simulating coolant injection on to hot gas was performed using a DPM (Discrete Phase Model). As a result of varying the coolant flow rate and number of injection holes, cooling efficiency was improved when the number of injection holes were increased. In addition, the change of the coalescence frequency and spatial distribution of coolant droplets caused by the injection condition variation resulted in a change of the droplet diameter, affecting the evaporation rate of coolant. The evaporation was found to be a critical factor in the design optimization of the ejection system by suppressing the pressure drop while the temperature decreases inside the breech.

A Numerical Prediction for the Thermo-fluid Dynamic and Missile-motion Performance of Gas-Steam Launch System (수치모사를 통한 가스-스팀 발사체계의 열유동과 탄의 운동성능 예측)

  • Kim, Hyun Muk;Bae, Seong Hun;Bae, Dae Seok;Park, Cheol Hyeon;Jeon, Hyeok Soo;Kim, Jeong Soo
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2017.05a
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    • pp.591-595
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    • 2017
  • Numerical simulations were carried out to analyze thermo-fluid dynamic and missile-motion performance by using two-phase flow model and dynamic grid system. To analyze the interaction among the hot gas, coolant, and mixture flow, Realizable $k-{\varepsilon}$ turbulence and VOF(Volume Of Fluid) model were chosen and a parametric study was performed with the change of coolant flow rate. As a result of the analysis, pressure of the canister showed a large difference depending on the presence or absence of the coolant, and also showed a dependancy on the amount of coolant. Velocity and acceleration were dependent on the canister pressure.

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Thermo-fluid Dynamic and Missile-motion Performance Analysis of Gas-Steam Launch System Utilizing Multiphase Flow Model and Dynamic Grid System (다상 유동모델과 동적 격자계를 활용한 가스-스팀 발사체계의 열유동과 탄의 운동성능 해석)

  • Kim, Hyun Muk;Bae, Seong Hun;Park, Cheol Hyeon;Jeon, Hyeok Soo;Kim, Jeong Soo
    • Journal of the Korean Society of Propulsion Engineers
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    • v.21 no.2
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    • pp.48-59
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    • 2017
  • In this study, an analysis of the thermo-fluid dynamic and missile-motion performance was carried out through a numerical simulation inside the missile canister. Calculation was made in an analytical volume using dynamic grid and evaporated water was used as a coolant. To analyze the interaction among the hot gas, coolant, and mixture flow, Realizable $k-{\varepsilon}$ turbulence and VOF (Volume Of Fluid) model were chosen and a parametric study was performed with the change of coolant flow rate. As a result of the analysis, pressure of the canister showed a large difference depending on the presence or absence of the coolant, and also showed a dependancy on the amount of coolant. Velocity and acceleration were dependent on the canister pressure.

Thermo-fluid Dynamic Analysis through a Numerical Simulation of Canister (수치 모사를 통한 사출관 내부의 열유동 해석)

  • Kim, Hyun muk;Bae, Seong hun;Park, Cheol hyeon;Jeon, Hyeok soo;Kim, Jeong Soo
    • Journal of the Korean Society of Propulsion Engineers
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    • v.21 no.1
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    • pp.72-83
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    • 2017
  • A thermo-fluid dynamic analysis was performed through the numerical simulation of a missile canister. Calculation was made in a fixed analytical volume and fully evaporated water was used as a coolant. To analyze the interaction among the hot gas, coolant, and mixture flow, Realizable $k-{\varepsilon}$ turbulence and VOF(Volume Of Fluid) model were chosen and parametric study was performed with the change of coolant flow rate. It could be found that the pressure on the canister top nonlinearly increased with the increase of coolant flow rate. Temperature and coolant distribution were closely related to the flow behavior in canister. Temperature on the canister bottom indicated a decrease being proportional to coolant flow rate in early times but after a specific time, the temperature increased with the tendency being reversed. In addition, the early part of temperature showed a fluctuating phenomenon because of the overall circulatory flow of mixture gas.

MOLTEN CORIUM DISPERSION DURING HYPOTHETICAL HIGH-PRESSURE ACCIDENTS IN A NUCLEAR POWER PLANT (원자로 노심 용융물의 고압분출 및 비산 현상에 대한 수치해석적 연구)

  • Kim, Jong-Tae;Kim, Sang-Baik;Kim, Hee-Dong;Jeong, Jae-Sik
    • 한국전산유체공학회:학술대회논문집
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    • 2009.11a
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    • pp.121-128
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    • 2009
  • During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by a following jet of a high-pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet and released into other compartments of the NPP by a overpressure in the cavity. The fragments of the corium transfer thermal energy to the ambient air in the containment or interact chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical process. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. In this study, MC3D code was used to evaluate the dispersion rates in the APR1400 NPP during the high-pressure accidents. MC3D is a two-phase analysis code based on Eulerian four-fields for melt jet, melt droplets, gas and water. The dispersion rates of the corium melt depending on the RPV pressure were obtained from the MC3D analyses and the values specific to the APR1400 cavity geometry were compared to a currently available correlation.

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