• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2743-2759
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• 2020

A detailed computational fluid dynamics (CFD) simulation analysis model was developed using ANSYS CFX 16.1 and analyzed to simulate the basic design and internal flow characteristics of a 180 MW small modular reactor (SMR) with a natural circulation flow system. To analyze the natural circulation phenomena without a pump for the initial flow generation inside the reactor, the flow characteristics were evaluated for each output assuming various initial powers relative to the critical condition. The eddy phenomenon and the flow imbalance phenomenon at each output were confirmed, and a flow leveling structure under the core was proposed for an optimization of the internal natural circulation flow. In the steady-state analysis, the temperature distribution and heat transfer speed at each position considering an increase in the output power of the core were calculated, and the conceptual design of the SMR had a sufficient thermal margin (31.4 K). A transient model with the output ranging from 0% to 100% was analyzed, and the obtained values were close to the T_hot and T_cold temperature difference value estimated in the conceptual design of the SMR. The K-factor was calculated from the flow analysis data of the CFX model and applied to an analysis model in RELAP5/MOD3.3, the optimal analysis system code for nuclear power plants. The CFX analysis results and RELAP analysis results were evaluated in terms of the internal flow characteristics per core output. The two codes, which model the same nuclear power plant, have different flow analysis schemes but can be used complementarily. In particular, it will be useful to carry out detailed studies of the timing of the steam generator intervention when an SMR is activated. The thermal and hydraulic characteristics of the models that applied porous media to the core & steam generators and the models that embodied the entire detail shape were compared and analyzed. Although there were differences in the ability to analyze detailed flow characteristics at some low powers, it was confirmed that there was no significant difference in the thermal hydraulic characteristics' analysis of the SMR system's conceptual design.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.707-716
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• 2023

The influence of waste technological waters of thermal and fast reactors of Beloyarsk NPP (Russia) on the accumulation of ⁶⁰Co, ⁹⁰Sr and ¹³⁷Cs in macrophytes and ichthyofauna of the cooling pond has been studied. Critical radionuclides, routes of their entry into the ecosystem and periods of maximum discharge of radioisotopes into the cooling pond have been determined. It is shown that the technology of electricity generation at the Beloyarsk NPP, based on fast reactors, has a much smaller effect on the release of artificial radionuclides into the environment. Therefore, during the entire period of monitoring studies (1976-2019), the decrease in the specific activity of radionuclides of NPP origin in macrophytes was 13-25800 times, in ichthyofauna 1.5-44.5 times. The maximum discharge of artificial radionuclides into the Beloyarsk reservoir was noted during the period of restoration and decontamination work aimed at eliminating the emergencies at the AMB reactors of NPP. The factors influencing the accumulation of artificial radionuclides in the components of the freshwater ecosystem of the Beloyarsk cooling pond have been determined, including: the physicochemical nature of radioisotopes, their concentration in surface water, the temperature of the aquatic environment, the trophicity of the reservoir, the species of hydrobionts.

• 한국해양환경ㆍ에너지학회지
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• 제17권2호
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• pp.116-121
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• 2014

지열수를 온열원으로 사용하고, 해양심층수를 열침으로 사용하는 바이너리(binary) 지열 발전시스템은 기존 지열 발전시스템의 효율을 증대하기 위한 재열과정과 터빈출력을 향상시키기 위한 다단과정을 각각 또는 복합적으로 적용하여 다단재열재생사이클의 성능개선을 검토하였다. 사이클종류는 다단재열사이클(Multi Stage reheater cycle; MS), 다단재열재생사이클(Multi stage reheater regeneration cycle; MSR)이 있다. 작동유체는 R134a, R245fa를 적용하였으며 온열원의 온도가 $65^{\circ}C$, $75^{\circ}C$, $85^{\circ}C$ 열침은 $5^{\circ}C$를 적용하여 기본해석을 수행하였다. 본 논문에서는 온열원변화, 작동유체의 종류, 사이클의 종류에 따른 해양지열발전용 다단재열재생사이클의 출력 및 효율을 높이기 위한 해석을 수행하였다. 이를 열역학적 사이클로 모사하기 위한 상용 프로그램인 Aspen HYSYS(V8.0)를 이용하여 해석을 진행 하였다. 작동유체는 R245fa가 R134a보다 우수한 성능을 보였으며, 온열원의 변화와 각각의 사이클 종류에 따라 적절한 작동유체가 있음을 확인 할 수 있었다. 사이클의 출력 및 효율은 각각 MS사이클과 MSR사이클에서 좋은 성능을 나타냈다.

• 플랜트 저널
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• 제18권1호
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• pp.55-61
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• 2022

본 연구에서는 역청탄으로 설계된 870MW급 유연탄 화력발전소를 대상으로 발전기 출력, 연소조건, 통풍조건을 일정하게 유지하면서 역청탄과 아역청탄을 혼합하여 연소함에 따른 슬래깅 발생 영향을 분석하였으며, 이에 따른 보일러 성능에 영향을 주지 않는 허용 가능한 혼탄 방안을 제시하였다. 아역청탄의 혼합 비율을 10%, 20%, 40%, 60%, 80% 등으로 조정하여 원소분석, 공업분석, 회융점 변화, 슬래깅 지수 등을 확인하였고, 적정 혼탄 조건은 아역청탄은 40% 이하로 혼탄하고, 회의 산성분 대비 염기성분 비율은 0.4이하 또는 1이상, 총 알칼리는 3.5이하, 융점 슬래깅 지수는 1,345℃ 이상, 원소분석 시 회함량은 13% 이하, 공업분석 시 회함량은 15% 이하, 초기용융점은 최소 1,200℃ 이상이어야 바람직하다고 판단된다.

• 한국산학기술학회논문지
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• 제18권6호
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• pp.29-36
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• 2017

본 논문은 열병합 복합발전이란 하나의 프로세스에서 전기 또는 기계 동력과 열에너지의 두 형태를 생산하는 것이다. 가스터빈 열병합 발전 시스템의 각 구성부의 성능을 변수로 전체 시스템의 연료 소모와 각 구성부의 열과 전기의 성능을 표현하여야 한다. 전체시스템은 상부 시스템인 가스터빈 2대와 하부시스템인 열회수 증기발생기(HRSG) 2대, 증기터빈 1대, 지역난방열교환기 2대로 구성되어 있다. 가스터빈 열병합 복합발전시스템에서 가동시간 기준 10,000시간 후 성능시험을 각종 시험장치 설치 및 ASME PTC 46에 준한 성능시험으로 실시하였고, 발전소 전체의 종합출력과 효율에 대한 성능을 분석하였다. 이러한 성능시험 실시자료를 기초로 시험성능을 비교하여 성능변화 값을 확인하였다. 이 논문에서 가스터빈, 열회수 증기발생기, 증기터빈의 열역학적 시스템 해석을 통하여 이론적 결과 값을 산출하였다. 비교 대상은 전체 시스템의 생산열량과 대기로 배출되는 열량을 이론값과 실험값을 비교하였고, 전기출력 및 열 출력에 대한 효율을 이론값과 실제 값을 비교하였다. 가스터빈 열병합 복합발전소 성능 특성에 대한 시험결과를 열역학적 효율 특성과 비교하였으며, 0.3%의 오차를 보였다.

• 한국조경학회지
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• 제33권2호
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• pp.100-110
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• 2005

The Korea South-East Power Co., Ltd.(KOSEP) held a design competition for Energy Theme Park at Yeong-Heung power plant in October, 2004. The site is located in 980-1 Oe-ri, Yeong-Heung myun, OngJin gun, Incheon City and has an area of $54,450m^2$. Design objectives of KOSEP were to make environmentally sustainable space, to build a symbolic and gathering place for community members and visitors, to make a tourist spot of Yeong-Heung Island linked with adjacent sight spots in OngJin gun, and to elevate an identity and status of the KOSEP by creating a landscape correspondent to the concept of the building design. The spatial concept of this project was developed by expressing a circular course of energy, named 'energy circle' and accounting for principles of energy generation. By interpreting 'energy circle' and principles of energy generation, and applying it to the site, the design met the various desires of the KOSEP. This design consists of seven theme spaces; the future energy plaza, the wind plaza, the light plaza, the thermal power plaza, a water strider dam, a ecological pond and the stratum plaza. These theme spaces are consecutively placed along the circular path which surrounds the public information building and to represent how power plants generate energy in each space and diverse design techniques and special effects are used.

• 동력기계공학회지
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• 제13권6호
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• pp.95-101
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• 2009

The generator for gas turbine power generation consists of the rotor which generates magnetic field, the winding coil which is the path for the field current and the wedge and retaining ring which prevents the radial movement of the coil. Relatively severe deformation was observed at the coil end section during the inspection of the generator for peaking-load operation, and the thermal-electricity and the centrifugal force were evaluated by the simple modeling of the windings to find the cause. But the simulation stress was not sufficient to induce the coil plastic deformation. The analysis result seems to be applicable to the base-load generators which runs continuously without shut down up to a year, but there had been more deformation than simulated for the generator which is started up and shut down frequently. The cause of the coil deformation was the restriction of the expansion and shrinkage. The restriction occurs when the winding coil shrinks, and the stress overwhelms the yield stress and cause the plastic deformation. The deformation is accumulated during the start-ups and shut-downs and the thermal growth occurs. The factors which induce the coil restriction during the expansion and shrinkage should be reduced to prevent the unallowable deformation. The resolutions are cutting off the field current earlier during the generator shut-down, modifying the coil end section to remove the stress concentration and making the insulation plate inserted between the coil end section and the retaining ring have the constant thickness.

• 설비공학논문집
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• 제24권3호
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• pp.281-287
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• 2012

The internal oxide scale of twelve superheater and reheater tubes were tested which were serviced for 30,000~120,000 hours in thermal power plants. The oxide scale was formed in three layers. The Cr-rich area was observed beneath the original metal surface. The hematite ($Fe_2O_3$) phase was formed on the outer surface. The intermediate layer was magnetite ($Fe_3O_4$). The thickness of Cr-rich layer was about half of the total scale. All layers grew during the operation hour of the plant. The thickness of thickest scale was 0.2mm in superheater tubes. This can increase the tube metal temperature about $7^{\circ}C$ more than initial state. $7^{\circ}C$ tube metal temperature can reduce tube life about 30%, but the boiler tube's design margin is big enough therefore it has been analyzed that it would not effect on the life span.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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• pp.134-136
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• 2005

This paper deals with the standard logic symbols with which the engineer will design the control strategy and loop for the utility boiler of the next generation thermal power plant For this purpose, we review the existing international standards for logic symbols. which include ISO, ANSI, and older SAMA. From this review, it is possible to design the standard logic symbol that will be used in the following design phase. The designed standard logic symbols are supposed to provide the logic design with independence from the specific hardware that will be employed in the phase of construction.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.155.2-155
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• 2002

A visual environment for system analysis codes (hereinafter called "ViSA") has been developed to support code users in their input preparations, code executions, and output interpretations. ViSA provides a more convenient way for base input data generation and modification on a user-friendly basis. It also provides on-line graphical displays to give an in-depth understanding of transient thermal-hydraulic behaviors in nuclear power plants. This paper presents the main features of ViSA.