• Journal of Advanced Marine Engineering and Technology
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• v.35 no.4
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• pp.443-450
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• 2011

Fuel gas compressor system is applied to medium FPSO. In order to avoid surge, this system used the anti-surge valves. When surge occurs it may lead to system's fracture. So anti-surge valves are evaluated structural strength and structural safety. Especially, in emergency mode, valves are must be guaranteed structural safety. In this study, structural strength and structural safety of anti-surge valve was evaluated using the numerical simulation. Unigraphics NX 4.0 was used as Geometrical models, structural strength and structural safety calculation were carried out by ANSYS Workbench 12.1. The ASME Boiler & Pressure Vessel Code is refer to allowable strength and safety factor of the valves.

• Journal of the Korean Institute of Gas
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• v.19 no.5
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• pp.1-6
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• 2015

In this paper, the strength safety of a fuse cock main body has been analyzed by the finite element method. The stress and displacement behaviour characteristics have been investigated for thickness variations at the region of (T) between a ball valve and a fuse cock safety connector. The FEM analyzed results recommend that the optimized thickness at the region of (T) is from 1.55mm to 1.6mm for the supplied gas pressure of 1.5~3.5MPa. This is considered for the optimized strength safety and light weight of a fuse cock main body.

• Journal of Chest Surgery
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• v.23 no.4
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• pp.622-639
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• 1990

The use of aortic valve homograft has been developed since 1962 when Ross and Barratt - Boyes independently replaced a diseased aortic valve with an orthotopically inserted homograft valve. And also surgical treatment of complex congenital cardiac malformations utilizing homograft extracardiac conduit has been tried with better result than any other prosthetic material. The present study was undertaken to clarify the safety tissue viability, sterility, after following our protocol of procurement of heart, dissection of aortic and pulmonic homograft, sterilization, cryopreservation, thawing and dilution, and transplantation on experimental animal, sheep. Tissue viability of valve and great artery was assessed by tissue culture. Sterility was evaluated by bacterial and fungal culture. The method used was proven no deleterious effect on the integrity of the valve. Tissue culture of valve tissue before, and after cryopreservation process resulted that active fibroblast growth was observed from homograft sterilized with antibiotics. And culture of the transplanted homograft from sacrificed animal showed active fibroblast growth. Pathologic examination of implanted valve tissue from sacrificed sheep showed mild calcification and minor change, but there were moderate and severe calcification of wall of great arteries.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.13 no.5
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• pp.1963-1968
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• 2012

In this research paper a hydraulic valve meter for the measurement of water pressure in fields was designed by using three dimensional automatic design program CATIA. And, also computational fluid dynamics was applied to the designed hydraulic valve meter in order to obtain flow distributions due to internal pressures. This analytical results will be provided as fundamental data in the development of new concepts of hydraulic valve meter and the hydraulic valve meter in development may reduce valve checking times and improve safety by preventing accidents earlier.

• Journal of the Korean Society of Safety
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• v.32 no.1
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• pp.60-65
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• 2017

In this study, a simplified FE model for evaluating seismic performance of valve support was suggested and an apparatus for a real structure testing was developed. The seismic performances of three different types of valve supports were evaluated by the real structure testing. By comparing the results between the real structure testing and FEA using the simplified FE model, it was verified that the suggested simplified FE model can be utilized for comparative evaluation of seismic performance of valve supports.

• Proceedings of the KSME Conference
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• 2003.11a
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• pp.881-886
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• 2003

In spite of its simple design, structure and operating mechanism, swing check valves are one of the critical components which adversely affect the safety of the nuclear power plants if they fail to function properly. Therefore, it is important to evaluate the performance condition of the swing check valves in safety-related systems. The performance characteristics of swing check valves include opening characteristics, the minimum required flow velocity, the pressure drop at design flow, the disc stability, and the effect of the upstream disturbances. Among factors to identify the performance of a swing check valve, a method to evaluate the opening characteristics and the minimum required flow velocity, which guarantees to fully open the disc and hold the disc without motion, are presented to determine the operating region of the swing check valve, such as stable, tapping, or oscillation. Based on the determined operating region and opening characteristics, the simple methods of wear and fatigue analyses of the specific parts of the valve are also described.

• The KSFM Journal of Fluid Machinery
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• v.4 no.4 s.13
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• pp.16-21
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• 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.

• Journal of the Korean Society of Safety
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• v.30 no.6
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• pp.48-55
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• 2015

A variety of safety issues were investigated for chemical reactors using a toluene solvent in case of a fire at small to middle scale chemical plants. The issues covered the operation of pressure-relieving valves and the subsequent discharges of the toluene to the atmosphere either directly or through an absorber, which represent the current practice at most small chemical plants. It was shown that the safety valve on the reactor may not operate within about twenty minutes after an external fire breaks out, but, once relieved, the toluene vapor released directly to the atmosphere may form a large explosion range on the ground. It was also shown that if the discharge is routed to an existing absorber used for the scrubbing of volatile organic compounds or dusts, the column may not operate normally due to excessive pressure drops or flooding, resulting in the hazardous release of toluene vapors. This study proposed two ways of alleviating these risks. The first is to ruduce the discharge itself from the safety valve by using adequate insulation and protection covers on the reactor and then introduce it into the circulation water at the bottom of the absorber through a dip linet pipe equipped with a ring-shaped sparger. This will enhance the condensation of toluene vapors with the reduced effluent vapors treated in the packing layers above. The second is to install a separate quench drum to condense the routed toluene vapors more effectively than the existing absorber.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.659-660
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.140.2-140
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• 1999