• 제목/요약/키워드: Passive Safety

검색결과 401건 처리시간 0.025초

부하설비의 고조파 저감을 위한 수동필터 설계 (Design of Passive Filter for Harmonic Elimination of the Load System)

  • 손재현;강창섭;이홍기;윤철섭
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 1997년도 하계학술대회 논문집 A
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    • pp.276-278
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    • 1997
  • The aim of this study is to design a passive filter for the elimination of harmonics. For this design, the harmonics wave generating from the six pulse rectifier was measured and its characteristics were analyzed. We also calculated the quantity of harmonic current by changing the system operational conditions. According to this field data and calculated results. we determined the elements of the passive filter. The simulation results indicate the efficiency of designed passive filter.

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Conceptual Safety Design Analyses of Korea Advanced Liquid Metal Reactor

  • Suk, S.D.;Park, C.K.
    • Nuclear Engineering and Technology
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    • 제31권6호
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    • pp.66-82
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    • 1999
  • The national long-term R&D program, updated in 1997, requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor(KALIMER), along with supporting R&D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R&D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of HAMMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation.

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자기방전식제건기에 의한 대전물체의 제전 및 방전특성 (A Study on Characteristics of De-electrification and Discharge of Self-Discharged Electrostatic Reducer)

  • 박수덕;이동훈
    • 한국안전학회지
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    • 제10권2호
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    • pp.72-76
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    • 1995
  • An electrostatic passive neutralizer without HV power source has been used widely to reduce charges on insulators such as running plastic films, papers and cloths, but its elimination characteristics and safely have been hardly investigated in detail. Especially, an operation of the passive neutralizer depends primarily on the charged insulator and the elimination ability does not depend on only the neutralizer, because an electrostatic elimination is caused by corona discharges occurring between the passive neutralizer and charged insulator. From a reason described above, the purpose of this study is to examine experimentally the elimination ability of the passive neutralizer. Experiments were made on the corona discharges between the passive neutralizer and charged insulator running at high velocity in practical field to make clear the setting condition of the passive neutralizer for operating effectively and safely. Results obtained from field experiments are presented in this paper.

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기니픽과 토끼에서 소성장 홀몬(BST)의 항원성에 관한 시험 (Antigenicity Test of Bovine Somatorophin(BST) in Guinea pigs and Rabbits)

  • 강경선;이영순
    • 한국식품위생안전성학회지
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    • 제6권3호
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    • pp.179-183
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    • 1991
  • 기니픽과 New Zealand White Rabbits에서 BST에 대한 항원성 시험을 국립보건안전연구원 예규에 따라 1) Active Systemic Anaphylaxis(ASA),2) Passive Systemic Anaphylaxis(PSA),3) Passive Cutaneous Anaphylaxis(PCA) 시험을 실시하여 다음과 같은 결과를 얻었다. 1) ASA, PSA 실험에서 anaphylaxis와 관련된 어떠한 특이적인 임상증상을 나타내지 않아 BST가 기니픽과 토끼에서 anaphylaxis를 유발하지 않는 것으로 생각된다. 2) PCA 실험에서 청색반점과 관찰되지 않은 것으로 보아 BST-specific IgE가 생성되지 않은 것으로 나타났다.

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Comparison on Safety Features among HTGR's Reactor Cavity Cooling Systems (RCCSs)

  • Kuniyoshi Takamatsu;Shumpei Funatani
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.832-845
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    • 2024
  • Reactor cavity cooling systems (RCCSs) comprising passive safety features use the atmosphere as a coolant, which cannot be lost. However, their drawback is that they are easily affected by atmospheric disturbances. To realize the commercial application of the two types of passive RCCSs, namely RCCSs based on atmospheric radiation and atmospheric natural circulation, their safety must be evaluated, that is, they must be able to remove heat from the reactor pressure vessel (RPV) surface at all times and under any condition other than under normal operating conditions. These include both expected and unexpected natural phenomena and accidents. Moreover, they must be able to eliminate the heat leakage emitted from the RPV surface during normal operation. However, utilizing all of the heat emitted from the RPV surface increases the degree of waste heat utilization. This study aims to understand the characteristics and degree of passive safety features for heat removal by comparing RCCSs based on atmospheric radiation and atmospheric natural circulation under the same conditions. It was concluded that the proposed RCCS based on atmospheric radiation has an advantage in that the temperature of the RPV could be stably maintained against disturbances in the ambient air.

고조파 수동필터의 설계 및 적용 (Design and Application of Harmonic Passive Filter)

  • 전정채;김재현;유재근
    • 한국산학기술학회논문지
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    • 제13권11호
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    • pp.5397-5402
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    • 2012
  • 고조파와 관련한 전력품질저하로 발생하는 전기설비사고 및 경제적 손실은 증가하고 있다. 수동필터는 고조파 문제를 해결하는데 경제적이고 효과적이지만 많은 엔지니어들은 그들의 전력시스템과의 직병렬 공진 문제 및 고조파 증폭 문제로 인해 사용하기를 꺼려한다. 본 논문은 수동필터가 잘 설계될 경우 고조파 문제를 해결하는데 매우 유용하다는 것을 보여준다. 고조파 수동필터 설계의 방법과 과정을 서술하였다. 그리고 100HP DC 모터, 압출 기계, 에어 압력기 등과 같은 비선형 부하로 인해 고조파 문제를 갖는 계통에 적용할 수 있는 수동필터를 설계하였다. 제시된 설계 방법과 절차에 대한 검증을 실험을 통해 입증하였다.

SAFETY ANALYSIS OF INCREASE IN HEAT REMOVAL FROM REACTOR COOLANT SYSTEM WITH INADVERTENT OPERATION OF PASSIVE RESIDUAL HEAT REMOVAL AT NO-LOAD CONDITIONS

  • SHAO, GE;CAO, XUEWU
    • Nuclear Engineering and Technology
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    • 제47권4호
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    • pp.434-442
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    • 2015
  • The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive residual heat removal (PRHR) system was designed to remove the decay heat. During accident scenarios with increase of heat removal from the primary coolant system, the actuation of the PRHR will enhance the cooldown of the primary coolant system. There is a risk of power excursion during the cooldown of the primary coolant system. Therefore, it is necessary to analyze the thermal hydraulic behavior of the reactor coolant system (RCS) at this condition. The advanced passive PWR model, including major components in the RCS, is built by SCDAP/RELAP5 code. The thermal hydraulic behavior of the core is studied for two typical accident sequences with PRHR actuation to investigate the core cooling capability with conservative assumptions, a main steam line break (MSLB) event and inadvertent opening of a steam generator (SG) safety valve event. The results show that the core is ultimately shut down by the boric acid solution delivered by Core Makeup Tank (CMT) injections. The effects of CMT boric acid concentration and the activation delay time on accident consequences are analyzed for MSLB, which shows that there is no consequential damage to the fuel or reactor coolant system in the selected conditions.

사고 영향 분석을 이용한 성능위주의 내화설계 (Performance Based Design of Passive Fire Protection Using Consequence Analysis)

  • 한동훈;이종호
    • 한국안전학회지
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    • 제19권1호
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    • pp.102-107
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    • 2004
  • Performance based design is a recent evolutionary step in the process of designing fire protection systems. In essence, it is a logical design process resulting in a solution that achieves a specified performance. Sometimes the prescriptive solutions presented in various codes and standards are too expensive or inflexible. Often the solutions do not and enables optimization of a solution for cost and function. In this study, performance based design was carried out to determine the extent of passive fire protection for oil terminal facilities. The results of performance based design were compared with those of prescriptive code based design. Performance based design is not always more economic than prescriptive code based design but provides more reliable and effective design that is fit for the purpose.

공냉-수냉 혼합냉각계통 개발 (Development of an Air-Water Combined Cooling System)

  • 권태순;배성원
    • 한국유체기계학회 논문집
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    • 제17권6호
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    • pp.84-88
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    • 2014
  • A long term passive cooling system is considered as the most important safety feature for the nuclear design after the Fukushima Daiichi nuclear power plant accident in 2011. The conventional active pump driven safety systems are not available during a station Black Out (SBO) accident. The current design requirement on cooling time of the Passive Auxiliarly Feedwater System (PAFS) is about 8 hours only. To meet the 72 hours cooling time, the pool capacity of cooling water tank should be increased as much as 3~4 times larger than that of current water cooling tank. In order to extend the cooling time for 72 hours, a new passive air-water combined cooling system is proposed. This paper provides the feasibility of the combined passive air-water cooling system. The current pool capacity of water cooling system is preserved, and the cooling capability is extended by an additional air cooler.