• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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• pp.203-205
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• 2005

A reactor protection system (RPS) plays the roles of generating the reactor trip signal and the engineered safety features (ESF) actuation signal when the monitored plant processes reach predefined limits. A Korean project group is developing a new digitalized RPS and the Cabinet Operator Module (COM) of the RPS which is used for the RPS integrity testing and monitoring by an equipment operator. A flat panel display (FPD) with a touch screen capability is provided as a main user interface for the RPS operation. To support the RPS COM user interface design, actually the FPD screen design, we developed a user interface style guide because the system designer could not properly deal with the many general human factors design guidelines. To develop the user interface style guide, various design guideline gatherings, a walk-though with a video recorder, guideline selection with respect to user interface design elements, determination of the properties of the design elements, discussion with the system designers, and a conversion of the properties into a screen design were carried out. This paper describes the process in detail and the findings in the course of the style guide development.

• 한국유체기계학회 논문집
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• 제8권6호
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• pp.15-25
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• 2005

Check valves playa vital role in the operation and protection of nuclear power plants. Check valves failure in nuclear power plants often lead to a plant transient or trip. The analysis of historical failure data gives information on the populations of various types of check valves, the systems they are installed in, failure modes, effects, methods of detection, and the mechanisms of the failures. A majority of check valve failures are caused by improper application. The experimental apparatus is designed and installed to measure the disc positions with flow velocity, Vopen and Vmin for 3 inch and 6 inch swing check valves. The minimum flow velocity necessary to just open the disc at a full open position is referred to as Vopen, and Vmin is defined as the minimum velocity to fully open the disc and hold it without motion. In the experiments, Vmin is determined as the minimum flow velocity at which the back stop load begins to increase after the disc is fully opened or the oscillation level of disc is reduced below $1^{\circ}$. The results show that the Vmin velocities for 3 inch and 6 inch swing check valves are about 27.3% and 17.5% higher than the Vopen velocities, respectively.

• 한국산업보건학회지
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• 제26권3호
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• pp.377-387
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• 2016

Objectives: The objective of this study was to describe the emotional labor experiences of ward nurses in Korea. Methods: The data were collected through focus group interviews with seven ward nurses. The phenomenological analytic method suggested by Colaizzi was used to analyze the data. Results: Four theme clusters and eleven themes emerged from the analysis. The first theme cluster, 'Terrible working environment' includes changes in the health environment and realities of nursing organization. The second theme cluster, 'Suppressed feelings' includes institutionalized power trip, patient-centered emotion management and burning. The third theme cluster, 'Tired body and mind' includes withdrawal, wounded self-esteem, burnout and turnover desicion. The fourth theme cluster, 'Want to be comforted' includes emotional control and wishing to live as a nurse. Conclusions: The findings of this study provide an understanding of the emotional labor experiences of ward nurses to explain their perceptions and language. The essence of the emotional labor of ward nurses is a negative working environment created by increased competition in the healthcare industry and the nature of nursing organization, and as a result their quality of life has fallen.

• 한국물환경학회지
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• 제25권6호
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• pp.964-971
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• 2009

In this paper, activated sludge settling was characterized based on field trip and zone settling tests. Plants used for this study include 5 conventional activated sludge processes and 3 A2O type treatment processes. The treatment capacities are in the range from 12,000 to $250,000m^3$/day. Total number of zone settling tests were 188 set and SVI values representing settling characteristics were from 100 to 300 mL/g. It was found out that zone settling velocity of these examined plant sludges can be approximated by mean values calculated by Keinath and Daigger/Roper models. Based on these three models, solid flux analysis were carried out in order to compare design criteria ($3.96{\sim}6.04kg/m^2-hr$) recommended by Korea Sewage Facility Design Guideline with two models used in USA. The results show that design criteria are only applicable for normal condition in settling characteristics (below SVI 100 mL/g). Solid flux analysis of surveyed plants indicates that most of the plants are operated underload conditions except several plants experiencing poor sludge settling problem. Most of the plants are operated under high sludge blanket depths (SBD).

• Nuclear Engineering and Technology
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• 제44권4호
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• pp.355-362
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• 2012

The aim of this study was to develop a bundle position-wise linear model (BPLM) to predict Pressure Tube (PT) diametral creep employing the previously measured PT diameters and operating conditions. There are twelve bundles in a fuel channel, and for each bundle a linear model was developed by using the dependent variables, such as the fast neutron fluences and the bundle coolant temperatures. The training data set was selected using the subtractive clustering method. The data of 39 channels that consist of 80 percent of a total of 49 measured channels from Units 2, 3, and 4 of the Wolsung nuclear plant in Korea were used to develop the BPLM. The data from the remaining 10 channels were used to test the developed BPLM. The BPLM was optimized by the maximum likelihood estimation method. The developed BPLM to predict PT diametral creep was verified using the operating data gathered from Units 2, 3, and 4. Two error components for the BPLM, which are the epistemic error and the aleatory error, were generated. The diametral creep prediction and two error components will be used for the generation of the regional overpower trip setpoint at the corresponding effective full power days. The root mean square (RMS) errors were also generated and compared to those from the current prediction method. The RMS errors were found to be less than the previous errors.

• 한국식생활문화학회지
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• 제8권2호
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• pp.125-137
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• 1993

The purpose of this study was to develop nutrition education program that promotes eating behavior of preschool children. 118 parents of preschool children were surveyed to understand of children's food preferences and prejudices. The preference for vegetable showed the lowest score(2.345) and fruit was the favorite food(4.11). These results imply the consequence of teaching balanced diet with emphasizing vegetables for preschoolers. Thus, nutrition education program including teaching material were developed to provide the preschoolers with cognitive, affective, and psychomotor activities in order them to the familiar with vegetables. The program were consisted of following five parts: 1. Read-A-Story includes six stories with follow-up activities. 2. Grow-A-Plant gives instructions for growing vegetables. 3. Play-A-Game stimulates children's imagination and learning. 4. Take-A-Trip suggests places to visit that grow, sell, and prepare vegetables. 5. Eat-A-Treat presents easy ways to prepare and enjoy vegetables. Twenty one-Standardized recipes for vegetable dishes were also developed for preschooler's luncheon and snack in daycare center.

• 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.

• 시스템엔지니어링학술지
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• 제17권2호
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• pp.49-60
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• 2021

The Core Protection Calculator System (CPCS) is vital for plant safety as it ensures the required Specified Acceptance Fuel Design Limit (SAFDL) are not exceeded. The CPCS generates trip signals when Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD) exceeds their predetermined setpoints. These setpoints are established based on the operating margin from the analysis that produces the SAFDL values. The goal of this research is to create a simplified CPCS that optimizes operating margin for I-SMRs. Because the I-SMR is compact in design, instrumentation placement is a challenge, as it is with Ex-core detectors and RCP instrumentation. The proposed CPCS addresses the issue of power flux measurement with In-Core Instrumentation (ICI), while flow measurement is handled with differential pressure transmitters between Steam Generators (SG). Simplification of CPCS is based on a Look-Up-Table (LUT) for determining the CEA groups' position. However, simplification brings approximations that result in a loss of operational margin, which necessitates compensation. Appropriate compensation is performed based on the result of analysis. FPGAs (Field Programmable Gate Arrays) are presented as a way to compensate for the inadequacies of current systems by providing faster execution speeds and a lower Common Cause Failure rate (CCF).

• 한국가스학회지
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• 제22권4호
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• pp.63-73
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• 2018

잉여전력 등을 활용한 에너지저장시스템 분야에 기술에 관심이 집중되고 혁신적인 기술진보가 이루어지고 있다. 다양한 에너지저장시스템 분야 중 가스액화 방식을 활용한 액화공기에너지저장 시스템은 상당히 성숙된 기술로 알려져 있고, 높은 단위 에너지 밀도와 설치에 따른 지형적 제약이 거의 없으며 수명이 긴 저장 시스템이라는 많은 장점에도 불구하고, 단일공정 (공기액화-재기화 사이클)의 낮은 사이클 효율로 인해 상업화에 한계가 있었다. 본 연구에서는 낮은 사이클 효율을 개선하고자 2종류의 냉매(R-600a 와 메탄올)을 이용한 냉매사이클을 공기 액화 공정에 활용하여 사이클 효율을 향상시키고, 공기 압축시 발생하는 압축열을 열매체유 순환 사이클에 이용하여 이를 액화공기 재기화 공정의 터빈 입구 온도를 높이는데 활용하여 전력생산량을 추가적으로 증가시킴으로써 사이클 효율을 획기적으로 향상시킬 수 있는 가능성을 Aspen HYSYS 공정 모사 프로그램을 활용하여 확인하였다.

• 플랜트 저널
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• 제4권3호
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• pp.66-72
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• 2008

The vibration of steam turbine is caused by Mass unbalance, Shaft misalignment, Oil whip and rubbing etc. But in turbine which is normally operated and maintained, the Mass unbalance component possesses the greatest portion. Our power plant has two steam turbines in capacity of 200 MW and 135 MW respectively and each turbine is supported by 6 journal bearings. However, we had many difficulties because the vibration amplitude of #3 and #4 Bearings was high during the start-up and operation mode change of steam turbine. But, with this study, we completely solved the vibration problem caused by the mass unbalance of #1 steam turbine. Until a recent date, #3 and #4 bearings which support high pressure turbine for #1 steam turbine had shown about $135{\mu}m$ in vibration amplitude (sometimes it increased to $221{\mu}m$ maximum. alarm: 6 mils, trip: 9 mils) at base load. After applying the study, they decreased to about $45{\mu}m$ maximum. It is a result from that we did not change the setting value of bearing alignment and only changed the assembly position of internal parts in Synchro clutch coupling rachet wheel which links between high pressure turbine and low pressure turbine, and increased the internal gap and machining of the Pawl cage surface. In the operation of steam turbine, if the vibration value increases by 1X, we should reduce the vibration of bearing by weight balancing. However, unless the vibration of bearing is declined by the balancing, we will have to disassemble and check the component and find the cause. In this study, we researched the way to lower mass unbalance that is 1X vibration component which has the greatest portion of vibration generated by steam turbine and we got good result by applying the findings of this study.