• 제목/요약/키워드: Safety demonstration

검색결과 208건 처리시간 0.027초

Safety Analyses of Process and Facility for the ACP Demonstration

  • You, Gil-Sung;Choung, Won-Myung;Ku, Jeong-Hoe;Cho, Il-Je;Kook, Dong-Hak;Lee, Eun-Pyo;Park, Seong-Won
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 2005년도 춘계학술발표회
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    • pp.293-294
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    • 2005
  • The safety analyses and evaluation works on the process and facility for ACP demonstration have been performed. The several safety factors, such as the risk, environmental, radiation, structural, criticality, were analyzed. The analysis results confirmed the reliability of the safety on the ACP process and facility during normal and accident conditions.

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THE BENCHMARK CALCULATIONS OF THE GAMMA+ CODE WITH THE HTR-10 SAFETY DEMONSTRATION EXPERIMENTS

  • Jun, Ji-Su;Lim, Hong-Sik;Lee, Won-Jae
    • Nuclear Engineering and Technology
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    • 제41권3호
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    • pp.307-318
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    • 2009
  • KAERI (Korea Atomic Energy Research Institute) has developed the GAMMA+ code for a thermo-fluid and safety analysis of a VHTR (Very High Temperature Gas-Cooled Reactor). A key safety issue of the VHTR design is to demonstrate its inherent safety features for an automatic reactor power trip and power stabilization during an anticipated transient without scram (ATWS) accident such as a loss of forced cooling by a trip of the helium circulator (LOFC) or a reactivity insertion by a control rod withdrawal (CRW). This paper intends to show the ATWS assessment capability of the GAMMA+ code which can simulate the reactor power response by solving the point-kinetic equations with six-group delayed neutrons, by considering the reactivity changes due to the effects of a core temperature variation, xenon transients, and reactivity insertions. The present benchmark calculations are performed by using the safety demonstration experiments of the 10 MW high temperature gas cooled-test module (HTR-10) in China. The calculation results of the power response transients and the solid core temperature behavior are compared with the experimental data of a LOFC ATWS test and two CRW ATWS tests by using a 1mk-control rod and a 5mk-control rod, respectively. The GAMMA+ code predicts the power response transients very well for the LOFC and CRW ATWS tests in HTR-10.

원자력폐기물 소각공정에서의 작업자 및 인근주민의 피폭선량에 따른 안전성 평가 (Safety Assessment of Nuclear Waste Incineration Process by Estimating Radiation Dose of Workers and Residential Individuals)

  • 서용칠
    • 한국안전학회지
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    • 제8권4호
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    • pp.165-174
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    • 1993
  • For the safety assessment of the demonstration-scale incineration plant for treating the combustible radioactive wastes, radiation doses of a worker and a residential individual were estimated. The demonstration plant showed a good performance of trial-burn tests using non-radioactive tracers with resulting In high mass reduction of around 40 times and very low emmission of dusts through a stack, which promised a high decontamination factor in an order of 10$^{7}$ . Based on the result s obtained from the trial-burns in the process, the estimation of radiation dose for workers and general publics near the plant was made using dose pathway calculation theories. The parametric values for calculation were selected from design and operational results of the process and from more conservative conditions In reference data. The estimated annual doses for workers and residential indivisuals were 3.07 $\times$ 10$^{-4}$ and 4.35 X 10$^{-8}$ $\mu$Sv/y, respectively, which were high enough to operate the process when comparing with the allowable dose limit in the regulation. The dose calculation models were quite applicable with showing an excellent safety for the process.

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노치가공법에 의한 기계적 피로결함 시험편 제조 (Fabrication of Mechanical Fatigue Flawed Specimen with Notch Processing)

  • 홍재근;박반욱
    • 연구논문집
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    • 통권32호
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    • pp.55-64
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    • 2002
  • Performance demonstration with real flawed specimens has been strongly required for nondestructive evaluation of safety class components in nuclear power plant. Specimen has been designed to produce mechanical fatigue flaw with tension stress and fatigue flaw has been produced to control stress and cycle, for suitable roughness. Notch condition is considered for control of fracture mode. After seal welding for fracture surface, final welding was performed to complete flaw specimen with GTAW(Gas Tungsten Arc welding) and FCAW(Flux Cored Arc Welding). It was demonstrated flaw size of flawed specimen by radiographic. testing and ultrasonic testing.

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집회시위 군집변화에 대한 연구 (Change of Regional Clusters on Assembly and Demonstration)

  • 주일엽
    • 시큐리티연구
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    • 제51호
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    • pp.293-313
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    • 2017
  • 본 연구는 2010년과 2015년 전국 16개 지역에서 발생한 집회시위 현황을 연구대상으로 선정하고 집회시위 발생현황에 대한 지역별 군집을 분석하여 그 변화를 알아보는데 그 목적이 있다. 이에 따른 연구결과는 다음과 같다. 첫째, 2010년 집회시위 발생현황에 대한 지역별 군집은 1단계로 (1) 광주, 충남, 인천, 충북, 경북, 대구, 강원, 제주, 대전, (2) 전남, 경남, 부산, 전북, 울산, 경기, (3) 서울 등 3군집으로 구분되고, 2단계로 (1) 광주, 충남, 인천, 충북, 경북, 대구, 강원, 제주, 대전, 전남, 경남, 부산, 전북, 울산, 경기, (2) 서울 등 2군집으로 구분된다. 둘째, 2015년 집회시위 발생현황에 대한 지역별 군집은 1단계로 (1) 울산, 강원, 충북, 충남, 인천, 경북, 전남, 광주, 제주, 대구, 대전, (2) 부산, 전북, 경남, (3) 서울, 경기 등 3군집으로 구분되고, 2단계로 (1) 울산, 강원, 충북, 충남, 인천, 경북, 전남, 광주, 제주, 대구, 대전, 부산, 전북, 경남, (2) 서울, 경기 등 2군집으로 구분된다. 셋째, 집회시위 발생현황에 대한 지역별 군집 변화는 2010년 '전남, 경남, 부산, 전북, 울산, 경기'는 '집회시위 관리지역(사회 문화, 노정, 경제 중심)', '서울'은 '집회시위 빈발지역'으로 구분되고, 2015년 '부산, 전북, 경남'은 '집회시위 관리지역(노정 중심)'으로, '서울, 경기'는 '집회시위 빈발지역'으로 구분된다. 이는 집회시위 관련 치안정책이 지역별 집회시위 증감 정도, 지역별 집회시위 군집 변화 등을 고려하여 가변적으로 수립, 시행될 수 있다는 것을 시사한다. 나아가 '인권을 지향하는 경찰'을 토대로 하는 효율적인 집회시위 관리에 도움이 될 수 있다.

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계통연계형 태양광발전시스템의 실증시험 분석 (Analysis of Demonstration Research for Grid-connected Photovoltaics System)

  • 박정국;김성결;이강연;조금배;백형래
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2004년도 춘계학술대회 논문집 전기기기 및 에너지변환시스템부문
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    • pp.205-207
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    • 2004
  • This paper presents experimental operation with utility invertactive 3kW photovoltaic generation system. And that describe configuration of utility interactive photovoltaic system which power supply for Demonstration experiment. The status of photovoltaic generation system components and interconnection and safety equipment will be summarized. This paper discusses property operation state which system endure division of power for demonstration experiment.

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태양광발전시스템의 실증연구를 통한 운용효율 분석 (Using Demonstration PV System for Operation Efficiency Analysis)

  • 박정민;김성결;정병호;조금배;백형래
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2003년도 추계학술대회 논문집
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    • pp.244-246
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    • 2003
  • This paper presents experimental operation with utility invertactive 3kW photovoltaic generation system. And that describe configuration of utility interactive photovoltaic system which power supply for Demonstration Complex. The status of photovoltaic generation system components and interconnection and safety equipment will be summarized. This paper discusses property operation state which system endure division of power for Demonstration Complex.

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주택보급형 3kW PV시스템 실증연구 (Demonstration analysis of residential 3kW PV System)

  • 박정민;문은아;김형석;임병옥;백형래
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2005년도 전력전자학술대회 논문집
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    • pp.734-736
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    • 2005
  • This paper presents experimental operation with utility invertactive 3kW photovoltaic generation system. And that describe configuration of utility interactive photovoltaic system which power supply for Demonstration experiment. The status of photovoltaic generation system comp-onents and interconnection and safety equipment will be summarized. This paper discusses property operation state which system endure division of power for demonstration experiment.

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