• Nuclear Engineering and Technology
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• 제28권3호
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• pp.257-264
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• 1996

The conventional Equipment Environment Qualification (EEQ) envelope is developed based on the containment responses during the design basis events. The Safety Depressurization System (SDS) design without In-containment Refueling Water Storage Tank (IRWST) adopted in the Ulchin 3&4 challenges the conventional EEQ envelope during long term Feed and Bleed (F&B) operation due to the direct discharge of high mass and energy into the containment. Therefore, it is necessary to confirm that the containment pressure and temperature history during the long term F&B operation does not violate the conventional EEQ envelope. However, this subject has never been quantitatively assessed before. To investigate the success path of long term F&B operation this paper analyzes the thermal hydraulic response of the containment and Reactor Coolant System (RCS) until the completion of depressurization and cooldown of RCS into Shutdown Cooling System (SCS) entry condition. It is found that the SCS entry condition can be reached within 6 hours without violating the EEQ curve by proper operation of SDS valves, High Pressure Safety Injection (HPSI) pumps and active Containment Heat Removal System (CHRS). The suggested strategy not only demonstrates the feasibility of long term F&B operation but also can be utilized in the preparation of Emergency Procedure Guidelines (EPGs)

• Nuclear Engineering and Technology
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• 제46권1호
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• pp.39-46
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• 2014

A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV) become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS) and the steam generator (SG) secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident.

• Nuclear Engineering and Technology
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• 제50권3호
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• pp.356-367
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• 2018

A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the $Prim{\ddot{a}}rkreislauf-Versuchsanlage$ (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project. These investigations address current safety issues related to beyond design basis accident transients with significant core heat up. This work presents a detailed analysis using the best estimate thermal-hydraulic code TRACE (v5.0 Patch4) of different SBO scenarios conducted at the PKL facility; failures of high- and low-pressure safety injection systems together with steam generator (SG) feedwater supply are considered, thus calling for adequate accident management actions and timely implementation of alternative emergency cooling procedures to prevent core meltdown. The presented analysis evaluates the capability of the applied TRACE model of the PKL facility to correctly capture the sequences of events in the different SBO scenarios, namely the SBO tests H2.1, H2.2 run 1 and H2.2 run 2, including symmetric or asymmetric secondary side depressurization, primary side depressurization, accumulator (ACC) injection in the cold legs and secondary side feeding with mobile pump and/or primary side emergency core coolant injection from the fuel pool cooling pump. This study is focused specifically on the prediction of the core exit temperature, which drives the execution of the most relevant accident management actions. This work presents, in particular, the key improvements made to the TRACE model that helped to improve the code predictions, including the modeling of dynamical heat losses, the nodalization of SGs' heat exchanger tubes and the ACCs. Another relevant aspect of this work is to evaluate how well the model simulations of the three different scenarios qualitatively and quantitatively capture the trends and results exhibited by the actual experiments. For instance, how the number of SGs considered for secondary side depressurization affects the heat transfer from primary side; how the discharge capacity of the pressurizer relief valve affects the dynamics of the transient; how ACC initial pressure and nitrogen release affect the grace time between ACC injection and subsequent core heat up; and how well the alternative feeding modes of the secondary and/or primary side with mobile injection pumps affect core quenching and ensure stable long-term core cooling under controlled boiling conditions.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2004년도 학술대회 논문집 정보 및 제어부문
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• pp.562-564
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• 2004

The containment leakage rate test performed on the nuclear power plants consists of following phases : pressurizing the containment, stabilizing the atmosphere, conducting a Type A test, conducting a verification test, depressurizing the containment. It takes more than 48 hours from the pressurization to the depressurization and the prediction of the results will help to prepare the next test phase. In this paper, to predict the leakage rate, the prediction methods based on the least square method are evaluated according to the input variables and the measurement period.

• 터널과지하공간
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• 제24권2호
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• pp.143-154
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• 2014

본 연구에서는 지오메카닉스모델을 이용한 가스하이드레이트 회수 생산 과정에서의 해리 발생 및 이에 따른 주변 퇴적층의 역학적 변형을 시뮬레이션 하였다. 지오메카닉스모델은 TOUGH+Hydrate와 FLAC3D 해석 코드를 순차적으로 반복해석하는 기법으로 감압법을 이용한 가스하이드레이트 회수 생산과정에서의 온도, 압력, 포화도 변화가 생산정 주변 퇴적층 내 유효응력, 강성 및 강도 변화에 미치는 영향을 고려할 수 있는 특징이 있다. 회수생산 방식에 따른 모델해석결과 비교를 통해, 감압법과 열자극법을 병행하는 경우 초기 생산량 증대를 가져올 수 있음을 보였다. 또한, 미고결 점토질 퇴적층에서의 회수생산 시 사암층에 비해 상대적으로 변형이 크게 발생함을 보였다.

• 터널과지하공간
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• 제25권2호
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• pp.133-143
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• 2015

가스하이드레이트는 천연가스가 저온 고압 상태에서 물과 결합하여 형성되는 고체 물질로 전세계 영구동토 및 심해저 퇴적층에 광범위하게 분포하는 것으로 파악되고 있다. 미국과 캐나다의 육상 영구동토에서 소량의 가스 생산 실증시험 사례가 보고된 바 있으나 심해저 가스하이드레이트로부터의 해상 가스 생산 사례는 일본 난카이 해구에서의 시험 생산이 유일하다. 본 연구에서는 일본 난카이 해구에서 실시된 해저 가스하이드레이트 함유층으로부터 감암법을 이용한 해리 가스 생산 사례를 분석하고 관련 핵심기술을 파악함으로써 국내에서 준비 중인 동해 울릉분지 유망 부지에서의 가스 시험생산에 활용코자 하였다.

• 자원환경지질
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• 제46권1호
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• pp.71-84
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• 2013

대부분의 GH는 전세계 해양퇴적물에서 대부분 산출되며 매장량은 $10^{13}{\sim}20{\times}10^{15}m^3$로 현재 세계 에너지 사용량을 기준으로 근 1,000년에 해당하는 양이다. MH는 전통석유가스자원를 대체할 미래 천연가스자원으로써의 잠재력이 있기 때문에 감압법, 화학첨가제 주입법, 열자극법, $CO_2$-메탄 치환법 등 채굴기술개발이 필요하다. 우리나라의 경우 2014년까지는 시험생산이 가능할 것으로 기대되고 있다. 이를 위하여 생산방법을 비교하고 GH의 분해에 따르는 반응이 복잡하기 때문에 이러한 현상을 예측하는 기술과 효과적이고 환경 친화적인 가스를 생산할 수 있는 기술을 개발하는 것이다.

• Journal of the Korean Wood Science and Technology
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• 제45권2호
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• pp.147-158
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• 2017

Among the energy consumption in building, the heating energy takes the largest part. Therefore, it is important to minimize the heat energy loss in building for the reduction of overall energy use in construction. The most important points for the minimization of energy loss in building are insulation and airtightness. Especially, in wood houses, airtightness is very important for energy saving as well as increase of durability. However, the researches on airtightness of wood buildings have been started recently and are very deficient especially in Korea. In this study, air leakage properties and airtightness performance were evaluated for light-frame wood houses built in Daejeon and Chungnam area. Total 7 houses were evaluated, among which four houses (Case 1 to Case 4) were in the construction stage before interior finish and the other three houses (Case 5 to Case 7) were after completion of construction work. The tests for airtightness were conducted by pressurization-depressurization method, and the factors included in the measurements includes air leakage rate at 50 Pa (CMH50), air change rate at 50 Pa (ACH50), equivalent leakage area (EqLA) and EqLA per floor area. As a result of this study, key air leakage points in wood houses were found to be the gaps between floor and wall, the holes for wiring and plumbing, the double glasses windows and the entrance doors. The average value of ACH50 for the houses after completion of construction work was $3.5h^{-1}$ that was similar to Europe standard ($3.0h^{-1}$). ACH50 was proportional to EqLA per floor area but inversely proportional to the internal volume, the net floor area and the area of window.

• 한국자원공학회지
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• 제55권6호
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• pp.670-687
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• 2018

본 논문에서는 미래 에너지로서 가스 하이드레이트를 이해하기 위해, 가스 하이드레이트의 구조, 물리/화학적 특성, 생성 기원과 세계 분포, 매장량과 생산기법, 하이드레이트의 지구환경적 영향에 대해 논의하였다. 하이드레이트의 구조에 대한 명확한 이해는 자연계에 매장된 하이드레이트의 특성 분석, 분포와 매장량 산출에 필수적일 것으로 판단된다. 안정적인 에너지 회수를 위해 고려해야 할 하이드레이트의 물리/화학적 특성으로는 하이드레이트의 상평형, 해리 엔탈피, 열전도도, 비열, 열확산도, 유체투과율 등이 있다. 하이드레이트의 물리/화학적 특성을 고려하여 개발된 생산기법으로는 감압법, 열자극법, 억제제 주입법, 맞교환기법이 있으며, 감압법이 현재까지 해상 및 육상 하이드레이트에 대해 모두 시험생산에 적용된 유일한 기법이다. 또한, 하이드레이트의 해리에 따른 온실가스 배출에 의한 지구환경적 영향의 가능성에 대해서도 고찰하였다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
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• pp.1520-1523
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• 1997

A rigorous dynamic simulation was performed in binary gas mixture H$_{2}$/CO (70:30 vol.%) to determinate start-up operating conditions of PSA(Pressure Swing Adsorption) processes. The rigorous dynamic model for the PSA process contains an Ergun equation for expressing the pressure drop in a bed, and valve equations to compute the boundary pressure change of the bed. As the result of the continuous dynamic simulation of 100 operating cyles in various initial conditions, the unsteady-state appeared in the early period and the cyclic steady-state came out about 20th cycle in feed condition and vaccum condition, and 30th cycle in pure H$_{2}$ condition. As time goes by valve equations made change the pressure at each end of the bed in ressurization, countercurrunt-depressurization and pressure equalization steps. The H$_{2}$ purity and the recovery is 99.99% and 86.73% respectively, which is slightly higher than the experimental data. Main contributiion of this study includes supplying fundamental technologies of handling combined variables PSA processes by developing rigorous models.