• Journal of Advanced Marine Engineering and Technology
• /
• v.21 no.5
• /
• pp.549-556
• /
• 1997

The inverse heat conduction problems is the calculation of surface heat transfer coefficients by utilizing measured temperature. The numerical technique of finite element analysis and optimizition is introduced to calculate temperatures and heat transfer coefficients. The calculated heat transfer coefficients and temperature distribution are good agreement with the results of direct analysis. The inverse method has been applied to the control valve of nuclear power plant.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
• /
• 2013.10a
• /
• pp.868-869
• /
• 2013

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.537-538
• /
• 2004

The performance of the ECWS was predicted for the anticipated operational occurrences. The inadvertent close of loop isolation valve is the most severe case for the five anticipated operational occurrences considered in this design and meets the design criteria of the ECWS. The correlation of critical heat flux for the geometry of three pins sub-channel analysis will be studied in the feature.

• Nuclear Engineering and Technology
• /
• v.25 no.2
• /
• pp.343-352
• /
• 1993

다목적연구로(KMRR)는 일반 발전용 원자로와는 매우 다른 특성을 가지고 있으며, 설계 개념 또한 특이하다. 위와 같은 특이한 설계 특성을 파악하기 위하여 열수력 실험을 수행하였으며 시운전 시험도 설계 개념의 입증에 중점을 두고 수행될 예정이다. 실증실험은 크게 설계 자료 생산을 위한 실험, 기기 설계 검증 시험, 시운전 성능 시험으로 나눌 수 있다. 설계 자료 생산을 위한 실험으로 핵연료의 열수력학적 특성을 규명하는 실험, 우회 유동에 의한 노심 출구 냉각수 상승 억제를 입증 또는 해석하기 위한 자료 생산용 실험 등이 이루어졌다. 기기 설계 검증 시험으로는 Pump 특성 시험, Flap valve 특성 시험 등을 들 수 있다. 또한, 시운전 성능 시험으로는 설계 개념을 입증하기 위한 여러 시험들이 행해질 예정이다. 이러한 실험들을 통하여 설계에 필요한 많은 자료들이 생산되었고, 시운전 시험을 통하여 설계를 검증하고 실제 운전에 필요한 많은 자료를 얻을 수 있으리라 기대된다. 본 기고를 통하여 이러한 실험의 중요성 및 내용에 대해 간략하게 기술하고자 한다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05b
• /
• pp.405-410
• /
• 1996

New methodology for mass and energy release assessment in LBLOCA post blowdown is needed and, first of all, the phenomenologically improved and quantitative assessments through experiment are essential. For tile experiment of a hot leg break LBLOCA in post blowdown, the test facility was set and its feature is that tile broken hot leg has two broken sections in the tore side and in the SG side respectively and a separation valve between the two in order to measure the release rate dividedly. Specially it was focused on whether the mass release through the SG side broken section happened or not. The mass release through the core side broken section is dependent on tile safety injection flow and that through the SG side broken section varies depending on several factors. The principal factor is the primary system pressure and the subfactors such as SI flow rate, SI temperature and initial primary pressure, may contribute, too.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.11 no.1
• /
• pp.39-44
• /
• 2015

The fracture toughness of 2.25Cr-1Mo cast steel (SA217-WC9) samples which were taken from the check valves of feed water piping of Korean Standard Nuclear Power Plant(KSNPP) was measured by Master Curve method. The measured $T_0$ reference temperature of SA217-WC9 steel was $-30^{\circ}C$. The obtained $T_0$ was compared to the derived value from Charpy impact test data following to SINTEP procedure. The heat-to-heat variation in fracture toughness of SA217-WC9 steel was observed. It was found that the low toughness of a heat of SA217-WC9 steel was attributed to the coarse MnS inclusion originated by high sulfur content as the results of microanalyses.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.05a
• /
• pp.562-567
• /
• 1995

The concept of VLDT (Variable Low DNBR Trip), a new CPC trip function, was proposed and applied to the events of increase in secondary heat removal, such as an excess feedwater event anti an IOSGADV (Inadvertent Opening S/G Atmospheric Dump Valve). Major assumption used in this study was no time delay to LOOP (Loss of Offsite Power) after turbine trip. In case of using this VLDT function, safety criterion of DNB would not be violated under the same condition as previous analysis without any change in thermal margin.

• Proceedings of the KSME Conference
• /
• 2001.06b
• /
• pp.718-723
• /
• 2001

PPM (Performance Prediction Methodology) developed by EPRI was introduced and applied to calculate the stem thrust of 3 and 4 inches flexible-wedge gate valves. The calculated stem thrusts of open and close strokes including cracking were compared with the results measured at in-situ differential pressure tests. The comparison has shown that PPM is an extremely conservative method to predict the minimum required stem thrust to operate motor-operated valves in a design basis accident condition of nuclear power plants.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
• /
• v.18 no.3
• /
• pp.202-210
• /
• 2006

In the nuclear power plant, emergency core coolant system (ECCS) is furnished at reactor coolant system (RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, thermal stratification phenomenon can be occurred due to coolant leaking in the check valve. The thermal stratification produces excessive thormal stresses at the pipe wall so as to yield thermal fatigue crack (TFC) accident. In the present study, when the turbulence penetration occurs in the branch pipe, the maximum temperature differences of fluid at the pipe cross-sections of the T-branch with thermal stratification are examine.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
• /
• 1999.11a
• /
• pp.149-154
• /
• 1999

This paper describes a passive safety injection system with free piston Stirling pump working withabundant decay heat in the nuclear reactor during the hypothetical accident. The water column in the tube assembly connected from the hot chamber to the cold chamber in the pump oscillates periodically due to thermal volume changes of non-condensable gas in each chamber. The oscillating pressure in the water column is converted into the pumping power with a suction-and-bleed type valve assembly. In this paper a dynamic model describing the frequency of oscillation and pumping pressure is developed. It was found that the pumping pressure is a function of the temperature difference between the chambers. Also, the frequency oscillation depends on the length of the tube with water column.