• 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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• 제56권6호
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• pp.2002-2010
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• 2024

Korea Atomic Energy Research Institute (KAERI) has operated an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), with reference to the APR1400 (Advanced Power Reactor 1400) for tests for transient and design basis accidents simulation. A test for a loss of coolant accident (LOCA) at the top of the reactor pressure vessel (RPV) had been conducted at ATLAS to address the impact of the loss of safety injections (LSI) and to evaluate accident management (AM) actions during the postulated accident. The experimental data has been utilized to validate system analysis codes within a framework of the domestic standard problem program organized by KAERI in collaboration with Korea Institute of Nuclear Safety. In this study, the test has been analyzed by using thermal-hydraulic system analysis codes, MARS-KS 1.5 and TRACE 5.0 Patch 6, and a comparative analysis with experimental and calculation results has been performed. The main objective of this study is the investigation of the thermal-hydraulic phenomena during a small break LOCA at the RPV upper head with the LSI as well as the predictability of the system analysis codes after the AM actions during the test. The results from both codes reveal that overall physical behaviors during the accident are predicted by the codes, appropriately, including the excursion of the peak cladding temperature because of the LSI. It is also confirmed that the core integrity is maintained with the proposed AM action. Considering the break location, a sensitivity analysis for the nodalization of the upper head has been conducted. The sensitivity analysis indicates that the nodalization gave a significant impact on the analysis result. The result emphasizes the importance of the nodalization which should be performed with a consideration of the physical phenomena occurs during the transient.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 1998년도 춘계 학술발표회 논문집
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• pp.159-165
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• 1998

한정된 자원의 효율적인 배분을 통하여 원자력발전소를 최적정비 하고자 신뢰도중심정비전략이 수립되고 있다. 본 연구에서는 영광 1,2호기 신뢰도중심정비 연구의 시범계통인 고압안전주입계통에 대하여 확률론적 안전성평가 모델을 이용하여 노심손상 빈도에 대한 중요도를 분석하였다 고압안전주입계통의 신뢰도 모델을 재구성하여 16개 초기사건에 대한 노심손상 빈도를 제정량화 하였고 고압 안전주입계통 고장수목에 모델링된 74개의 기본사건에 대하여 노심손상 빈도에 대한 중요도를 평가하였다.

• 설비공학논문집
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• 제18권3호
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• pp.202-210
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• 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.

• 한국산업보건학회지
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• 제19권3호
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• pp.280-287
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• 2009

High-tech microelectronics industry is known as one of the most chemical-intensive industries. In Korea, Microelectronics industry occupied 38% of export and 16% of working employees work in microelectronics industry. But, chemical information and health hazards of high-tech microelectronics manufacturing are poorly understood because of rapid development and its penchant for secrecy. We need to investigate on chemical use and exposure control. We Site-visits to 6 high-tech microelectronics manufacturing company which have cleanroom work using over 1,000kg organic solvents (5 semi-conductor chips and its related parts company, 1 liquid crystal display (LCD)). We reviewed their data on chemical use and ventilation system, and measured TVOCs (Total Volatile Organic Compounds) and carbon dioxide concentration. All cleanroom air passed through hepa filters to acheive low particle levels and only 1 cleanroom uses carbon filters to minimize the organic solvents exposures In TVOC screening test, Cleanroom for semi-conductor chips and its related parts company with laminar down flow system (e.g. class 1~100) showed nondetectable level of TVOCs concentration, but Cleanroom for liquid crystal display (LCD) with conventional flow system (e.g. class 1,000~10,000) showed 327 ppm as TVOCs. Acetone concentration in cleanroom for Jig cleaning, LC Injection, Sealing processes were 18.488ppm (n=14), 49.762 ppm (n=15), 8.656 ppm (n=14) as arithmetric mean. Acetone concentration in cleanroom for LCD inspection process was 40ppm (n=55) as geometric mean, where the range was 7.8~128.7ppm and weakly correlated with ventilation rate efficiency(r=0.44, p<0.05). To control organic solvents in cleanrooms, chemical and carbon filters should be installed with hepa filters. Even though their volatile organic compounds concentration was not exceed to occupational exposure limits, considering of entrance limited cleanroom environment, long-term period exposure effects and adverse health effects of cleanroom worker need further reseach.

• 한국지반신소재학회논문집
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• 제21권3호
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• pp.29-39
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• 2022

본 연구에서는 용탈 저감 효과가 있는 합성폴리머 실리카졸의 그라우트 성능을 평가하고, 기존 물유리계 SGR 주입재와 비교한 내용을 다루었다. 강도 및 내구성에 대한 실내실험 결과 합성폴리머 실리카졸는 물유리계 주입재 대비 2배 이상 높은 일축압축강도, 수축률 및 투수성에서 현저히 낮은 값을 보여주었고, pH는 먹는 물 수질기준인 8.5 이하였다. 용탈시험결과 합성폴리머 실리카졸의 Na₂O 용출량은 물유리계 주입재 대비 3~4배 작게 측정되었다. 이러한 결과로 보아 합성폴리머 실리카졸은 기존 물유리계 주입재보다 더 우수한 내구성 및 차수성을 가지는 것으로 판단된다.

• 에너지공학
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• 제17권2호
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• pp.67-76
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• 2008

열수력 종합효과 실험장치인 ATLAS가 한국원자력연구원에 구축되었으며, 최근 대형 냉각재 상실사고(LBLOCA)시의 재관수 현상에 대한 시험이 본격적으로 수행되었다. LBLOCA 재관수 단계에서 APR1400의 열수력 현상을 제대로 모사하기 위해서는 안전주입수 유량이 척도비에 맞춰 축척되어야 한다. 또한 ATLAS 장치에는 안전주입탱크(SIT) 내부께 자동제어 유량조절기구인 Fluidic Device가 장착되지 않았기 때문에 SIT의 고유량 및 저유량 주입 성능을 모사하기 위한 별도의 방안이 마련되어야 한다. 따라서 ATLAS의 주입 성능을 기준 발전소인 APR1400의 성능과 일치시키기 위하여 ATLAS 안전주입탱크의 특성 시험을 수행하였다. ATLAS SIT의 고유량 주입 성능은 주입 배관에 최적의 Orifice를 설치하여 일치시키고, 저유량 주입 성능은 유량조절밸브의 개도를 조절함으로써 일치시킬 수 있었다. 이러한 특성 시험을 통해 ATLAS 안전주입계통이 APR1400에서 요구하는 SIT 고유량 및 저유량을 잘 모의할 수 있다는 것을 확인할 수 있었다.

• Clinical and Experimental Otorhinolaryngology
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• 제11권4호
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• pp.281-287
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• 2018

Objectives. Regenerative treatment using stem cells may serve as treatment option for empty nose syndrome (ENS), which is caused by the lack of turbinate tissue and deranged nervous system in the nasal cavity. We aimed to assess the efficacy and safety of the autologous stromal vascular fraction (SVF) in the treatment of ENS. Methods. In this prospective observational clinical study, we enrolled 10 ENS patients who volunteered to undergo treatment of ENS through the injection of autologous SVF. Data, including demographic data, pre- and postoperative Sino-Nasal Outcome Test-25 (SNOT-25) scores, overall patient satisfaction, and postoperative complications, were prospectively collected. Nasal secretion was assessed using the polyurethane foam absorption method, and the levels of biological markers were analyzed in both ENS group and control group using enzyme-linked immunosorbent assay. The SVF extracted from abdominal fat was diluted and injected into both inferior turbinates. Results. Among the 10 initial patients, one was excluded from the study. Subjective satisfaction was rated as "much improved" in two and "no change" in seven. Among the improved patients, the mean preinjection SNOT-25 score was 55.0 and the score at 6 months after injection was 19.5. However, the average SNOT-25 score of nine participants at 6 months after injection (mean${\pm}$standard deviation, $62.4{\pm}35.8$) did not differ significantly from the baseline SNOT-25 score ($70.1{\pm}24.7$, P>0.05, respectively). Among the various inflammatory markers assessed, the levels of interleukin $(IL)-1{\beta}$, IL-8, and calcitonin gene-related peptide were significantly higher in ENS patients. Compared with preinjection secretion level, the nasal secretions from SVF-treated patients showed decreased expressions of $IL-1{\beta}$ and IL-8 after injection. Conclusion. Although SVF treatment appears to decrease the inflammatory cytokine levels in the nasal mucosa, a single SVF injection was not effective in terms of symptom improvement and patient satisfaction. Further trials are needed to identify a more practical and useful regenerative treatment modality for patients with ENS.

• 에너지공학
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• 제26권3호
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• pp.64-70
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• 2017

한국원자력연구원에서 제안한 혼합형 안전주입탱크 (Hybrid SIT)는 APR+ 원자로에 적용하기 위해 개발된 피동안전주입시스템이다. 본 연구는 대표적인 고압사고인 발전소정전사고 시 Hybrid SIT의 냉각성능을 평가하기 위해 열수력 안전해석 코드인 MARS-KS 코드를 이용한 예비해석에 대한 것이다. PAFS 구동이 정지되면, 열제거량이 감소하게 되어 가압기와 증기발생기의 압력이 상승하기 시작하며, 가압기의 압력이 안전감압계통(Pilot Operated Safety and Relief Valve) 개방 설정치인 17.03 MPa에 도달하면, 그와 동시에 Hybrid SIT의 증기격리밸브가 열림으로서 가압기 상단의 증기가 Hybrid SIT로 주입되게 된다. 주입된 증기에 의해 압력평형이 빠른시간 안에 이루어졌으며, 주입배관을 통해 냉각수가 주입 되었다. 발전소정전사고시 PAFS와 같은 열제거수단이 상실됨에도 혼합형 Hybrid SIT가 주입되는 시간동안은 노심의 수위가 유지됨을 확인할 수 있었고, 수위가 유지됨에 따라 노심 출구 온도(CET)의 상승을 방지함을 확인하였다.

• Nuclear Engineering and Technology
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• 제36권5호
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• pp.388-402
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• 2004

A phenomena identification and ranking table(PIRT) was developed for a main steam line break (MSLB) event for the Advanced Power Reactor-1400 (APR-1400). The selectee event was a double-ended steam line break at full power, with the reactor coolant pump running. The developmental panel selected the fuel performance as the primary safety criterion during the ranking process. The plant design data, the results of the APR-1400 safety analysis, and the results of an additional best-estimate analysis by the MARS computer code were used in the development of the PIRT. The period of the transient was composed of three phases: pre-trip, rapid cool-down, and safety injection. Based on the relative importance to the primary evaluation criterion, the ranking of each system, component, and phenomenon/process was performed for each time phase. Finally, the knowledge-level for each important process for certain components was ranked in terms of existing knowledge. The PIRT can be used as a guide for planning cost-effective experimental programs and for code development efforts, especially for the quantification of those processes and/or phenomena that are highly important, but not well understood.