• 제목/요약/키워드: Power Facility

검색결과 1,280건 처리시간 0.033초

Evaluation of MCC seismic response according to the frequency contents through the shake table test

  • Chang, Sung-Jin;Jeong, Young-Soo;Eem, Seung-Hyun;Choi, In-Kil;Park, Dong-Uk
    • Nuclear Engineering and Technology
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    • 제53권4호
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    • pp.1345-1356
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    • 2021
  • Damage to nuclear power plants causes human casualties and environmental disasters. There are electrical facilities that control safety-related devices in nuclear power plants, and seismic performance is required for them. The 2016 Gyeongju earthquake had many high-frequency components. Therefore, there is a high possibility that an earthquake involving many high frequency components will occur in South Korea. As such, it is necessary to examine the safety of nuclear power plants against an earthquake with many high-frequency components. In this study, the shaking table test of electrical facilities was conducted against the design earthquake for nuclear power plants with a large low-frequency components and an earthquake with a large high-frequency components. The response characteristics of the earthquake with a large high-frequency components were identified by deriving the amplification factors of the response through the shaking table test. In addition, safety of electrical facility against the two aforementioned types of earthquakes with different seismic characteristics was confirmed through limit-state seismic tests. The electrical facility that was performed to the shaking table test in this study was a motor control center (MCC).

Experimental testing and evaluation of coating on cables in container fire test facility

  • Aurtherson, P. Babu;Hemanandh, J.;Devarajan, Yuvarajan;Mishra, Ruby;Abraham, Biju Cherian
    • Nuclear Engineering and Technology
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    • 제54권5호
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    • pp.1652-1656
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    • 2022
  • Fire tests were conducted on cables using fire-retardant paint employed in nuclear power plants that transmit electrical power, control and instrument signals. The failure criteria of various power and control cables coated with fire retardant coating at three different coating thicknesses (~0.5 mm, 1.0 mm & 1.5 mm) were studied under direct flame test using Container Fire Test Facility (CFTF) based on standard tests for bare cables. A direct flame fire test was conducted for 10 min with an LPG ribbon burner rated at ten by fixing the cable samples in a vertical cable track. Inner sheath temperature was measured until ambient conditions were achieved by natural convection. The cables are visually evaluated for damage and the mass loss percentage. Cable functionality is ascertained by checking for electrical continuity for each sample. The thickness of cable coating on fire exposure is also studied by comparing the transient variation of inner sheath temperature along the Cable length. This study also evaluated the adequacy of fire-retardant coating on cables used for safety-critical equipment in nuclear power plants.

Optimum Design of the Wolsong Tritium Removal Facility

  • Ahn, Do-Hee;Lee, Han-Soo;Chung, Hong-Suk;Song, Myung-Jae;Son, Soon-Hwan
    • Nuclear Engineering and Technology
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    • 제28권4호
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    • pp.415-422
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    • 1996
  • Tritium removal from tritiated heavy water in a PHWR is the most effective way in reducing workers' internal dose and radioactivity emissions from Wolsong NPP. The optimum design of the Wolsong TRF (Tritium Removal Facility) was carried out using an approximate short-cut method with an assumption that the TRF, designed to extract 8 MCi per year of elemental tritium from a heavy oater feedstream, uses Liquid Phase Catalytic Exchange (LPCE) front-end process and Cryogenic Distillation (CD) process.

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옵셋 인쇄기계 동력규모 변화에 따른 소음 영향 평가 (The Noise Influence Assessment according to the Change of the Offset Type Print Machine's Power)

  • 구진회;권명희;이우석;이재원;박형규;김삼수;윤희경;이규목;정대관;서충열
    • 한국소음진동공학회논문집
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    • 제24권9호
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    • pp.682-686
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    • 2014
  • Nowadays, the needs to revise the classification criteria for noise emission facilities have been suggested by the related industries. Because there existed many reasonable factors in the criteria regarding the noise emission facilities. And the noise emission facility classification criterion of the print machine changed from 50 HP to 100 HP in 2013. But the increasement of the noise emission facility classification criterion of the print machine can cause adverse effects like the bigger noise. So, in this paper, we measured the print machine's sound power level according to the changes of the print machine's power to assess the adverse effects. The measurement method applied with KS I ISO 9614-2(1996). The corelation between the sound power level and the power of print machines was analyzed by regression analysis. In this paper, we found that the sound power level of the print machines can increase about 1.3 dB in the condition of that the power of print machine increases from 50 HP to 100 HP. And we found that the sound power level of the print machines can increase about 1.0 dB for a increasement of 1,000 SPH(sheet per hour) of printing speed. The noise emission characteristics of print machine stuied in this paper will be useful to design the noise reduction plan in the future.

계통 안전성을 고려한 원자력발전의 부하추종 요건연구 (A Study on Requirement of Nuclear Power Plant Load Following Operation Condition Considering Power System Security)

  • 이현철;백영식;이근준
    • 전기학회논문지
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    • 제61권11호
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    • pp.1565-1570
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    • 2012
  • Nuclear power generation is increasing domestic power supply ratio by lower CO2 emission and fuel prices. Currently, nuclear power generator has been operated with maximum power output. Therefore, nuclear power generator could be no effect to managing the reactive power reserve on power system. The reactive power reserve is calculated to the difference between maximum facility and operation generation capacity of the power system. This paper was proposed that load following of nuclear power is control by using 15-bus power system model. In the simulation result, power system is shown to safety state by operating load following of nuclear power generator. This method has be improved the supplied reliability through economic and efficient operation.

발전용 역청탄 및 아역청탄의 파일롯 연소특성 평가 (Combustion Characteristics of Imported Bituminous & Subbituminous Coal in a Pilot Scale Test Facility)

  • 김현희;박호영;임현수;백세현;김태형;김영주;공지선;이정은
    • 에너지공학
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    • 제23권4호
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    • pp.207-214
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    • 2014
  • 고급탄의 고갈에 따라 석탄화력발전소에서의 저급탄 혼소가 필수불가결하게 되었다. 본 연구에서는 국내에서 수입되는 석탄 중에서 대표적으로 사용되는 역청탄과 아역청탄에 대한 연소특성을 0.7MWth 파일롯 연소실험장치를 사용하여 측정, 분석하였다. 과잉공기비가 1.2인 상태에서 축방향 및 반경방향의 노내 가스온도 및 주요 가스농도를 측정하였으며, 역청탄 연소시 반응로 내의 입자 샘플링을 수행하였다. 두 탄종의 주반응영역은 노 상부의 스월버너로부터 약 1m 근방에서 형성되었으며, 노 하류에서는 완전 확립된 온도와 농도분포를 나타내었다. 포집된 역청탄의 고체입자 분석으로부터 주반응영역 이후에 완전한 탄소전환이 이루어진 것을 확인하였다.

수상 태양광발전시설의 심리적 변화 및 시각적 선호도 - 뇌파(EEG) 및 SD법을 중심으로 - (Psychological Changes and Visual Preferences of Floating Solar Photovoltanics - Focusing on EEG and SD Methods -)

  • 짱위지에;정태열;서성혁
    • 한국조경학회지
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    • 제51권2호
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    • pp.131-142
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    • 2023
  • 탄소배출을 감축하기 위한 태양광발전시설은 산림, 농지, 도시, 수상 등에 우후죽순처럼 설치되고 있다. 그러나 태양광발전시설의 설치 이후 관찰자에게 미치는 시각적 선호도 및 심리적 영향에 관한 연구는 부족한 실정이다. 이에 본 연구는 한국 최대 규모의 수상 태양광발전시설 합천댐을 대상으로 근경, 중경, 원경의 시(視)거리에 따라 촬영을 실시하였다. 획득한 이미지를 포토샵을 통해 수상 태양광발전시설을 유무에 대해 비교하여 총 50명 연구 대상자의 뇌파(EEG) 및 설문지 분석을 통해 수상 태양광발전시설 설치 전후의 심리적 변화 및 시각적 선호도를 분석하였다. 결과를 요약하면 다음과 같다. 첫째, 수상 태양광발전시설의 설치에 따라 연구 대상자의 심리적 변화 및 시각적 선호도에 소극적인 영향을 끼치고 있다. 둘째, 수상 태양광발전시설의 설치에 따른 심리적 변화는 연구대상자의 국적/성별/전공과는 상관없이 거의 모든 연구대상자들에게 영향을 끼치는 것으로 판단되었다. 셋째, 수상 태양광발전시설의 설치에 따른 시각적 선호도는 낮으며, 이는 수상 태양광발전시설로 인해 경관의 '친근성' 및 '자연성'에 부정적 영향을 주는 것을 알 수 있다. 또한 이런 시각적 선호도의 변화는 연구대상자의 성별/전공에 따른 차이가 있는 것으로 나타났다. 넷째, 시(視)거리에 따른 수상 태양광발전시설이 관찰자에게 끼치는 심리적 변화 및 시각적 선호도는 근경이 중경과 원경보다 높은 영향을 미치는 것으로 나타났다.

방사선 환경내에서의 CCTV 카메라 개발 (Development of CCTV Camera in Radiation Environment)

  • 소수길;이용범;최영수;김성구;변의교;유승욱;하달규
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 1999년도 전력전자학술대회 논문집
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    • pp.403-406
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    • 1999
  • For a man's approaching limitation in radiation environment, all work must be performed with remoted system to ensure worker's safety and reliability from radiation damage. The remoted system is mostly used in visual observation CCTV system. In high radiation environment of unclear power plant, RI(Radio-isotope) facility, medical radiation treatment facility must be used to radiation tolerant CCTV cameras for radiation damage. We have studied a radiation basic performance of camera components and CCTV cameras to develop radiation tolerant CCTV cameras. As a result, we are able to design a radiation tolerant camera of 108 rad total dose.

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전력설비 정지관리 기준에 따른 전력설비 정지종류 분류 및 년도별 정지율 통계 (Power facility Stop-type Classification and Yearly Rate of Stop Statistics Following Power facility Stop-management Standard)

  • 홍희정;김종혁;정구형;강동주;김발호
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2008년도 제39회 하계학술대회
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    • pp.602-603
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    • 2008
  • 본 논문에서는 전력계통의 안정적인 운영과 전기품질을 확보하고 전력수급 기본 계획 수립 등 전력설비 투자 계획에 활용하기 위하여 최근 새롭게 개정된 전력설비 정지관리 기준(電力設備 停止管理 基準)에 따라 전력설비 정지종류를 분류해 본다. 또한 계획정지, 비계획정지로 구분했던 2006년도 발전설비의 정지일수와 정지량등을 알아보고, 계획정지, 비계획정지, 운영예비초과정지 등으로 세분화된 분류에 따른 2007년도의 정지율을 계산하여 본다.

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선조립공법을 활용한 원전구조물 철근모듈화 Mock-up 실험연구 (Mock-up Test for Nuclear Power Plant Rebar Modulation Applying Febrication)

  • 임상준;이병수
    • 한국건축시공학회:학술대회논문집
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    • 한국건축시공학회 2015년도 춘계 학술논문 발표대회
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    • pp.13-14
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    • 2015
  • To minimize construction of nuclear facility, it is required to reduce reinforcing bar amount and solve reinforcing bar concentration and for this, it is necessary to develop appication design technology and modular of high strength reinforcing bar. Hence, KHNP reduces excessive reinforcing bar amount which can cause possibility of poor construction of concrete through design standard development and modular of nuclear facility structure using high strength reinforcing bar to raise economics and has its purpose to maintain high-level safety and durability as they are. After reviewing the rebar drawing of the NPP structures and performing the mock-up test, the rebar modulation method in the various area of the NPP Structure has been established.

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