• Title/Summary/Keyword: 원전구조물

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국내외 지진발생 현황과 국내원전의 안전성 평가

  • 김영식
    • Nuclear industry
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    • v.15 no.7 s.149
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    • pp.56-59
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    • 1995
  • 국내 원전은 내진성 확보를 위해 부지의 선정단계에서는 원전의 예상입지를 중심으로 320km 내의 지진특성과 과거지진기록을 면밀히 분석$\cdot$반영하고, 부지중심으로 반경 8km 내에 대해서는 정밀지질조사를 실시하여 단층대나 연약지반 등 지진발생 가능지역은 제외시키고 있으며, 구조물의 설계와 설치시에는 과거의 지진발생기록을 근거로 하여, 발전소 인근지역에서 발생이 가능한 최대 지진과 부지의 지반특성, 그리고 구조물의 하중 등을 복합적으로 고려하여 내진설계하고 있다. 가동중에는 각종 자동지진감시계통이 지진발생 여부를 지속적으로 계측한 후에, 설계지진값의 절반인 지반가속도 0.1g 이상의 지진을 감지하면 자동경보장치를 작동시켜 즉각 운전이 정지되도록 설계되어 있다.

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원전 수명 관리 연구 및 주기적 안전성 검토

  • 정일석
    • Nuclear industry
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    • v.19 no.11 s.201
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    • pp.39-46
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    • 1999
  • 국내 가동 원전의 운전 연수가 증가함에 따라 장기 사용 원전의 안전성 향상과 수명 관리 연구가 진행되고 있다. 원전 수명 관리는 발전소 운전 안전성과 성능을 유지하면서 최적 경제 시점인 최적 수명까지 발전소를 운전하기 위한 제반 기술 활동이다. 적절한 수명 관리로 원전을 최적 수명까지 운전하더라도 발전소는 노화에 의해 운전 안전성이 영향을 받거나 저하되지 않아야 한다. 발전 설비의 노화에는 실제의 기기나 구조물이 경년 열화에 의해 노화되는 물리적 노화와 설계 기술의 발달과 새로운 안전 개념의 적용으로 기존 기술이 낙후하는 비물리적 노화로 구분할 수 있다. 물리적 노화는 기기$\cdot$구조물$\cdot$계통의 물리적 상태 변화로 성능을 저하시키고, 비물리적 노화는 발전소 계통의 안전 개념$\cdot$기준$\cdot$기술이 새롭게 변화되지 않은 것이다. 본 논문에서는 물리적 노화는 수명 관리 연구, 비물리적 노화는 안전성 관리의 측면에서 검토하였고, 두 분야의 국내외 연구 현황$\cdot$개념$\cdot$추진 방법$\cdot$상호 관계 등을 살펴보고, 상호 유기적인 관계를 보완 할 수 있는 제도적 장치 도입 및 적용 방안에 대해 논하였다.

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Performance Evaluation Test for Applying the Mechanical Development of the High-Strength Reinforcing Bars to the Nuclear Power Plant Structures (고강도철근 기계적정착의 원전구조물 적용을 위한 성능평가실험)

  • Lee, Byung-Soo;Bang, Chang-Joon;Lim, Sang-Joon;Kim, Seok-Cheol
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2012.11a
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    • pp.197-198
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    • 2012
  • If the mechanical development be applied to the Nuclear Power Plant Structures instead of the standard hook development, the problem of overcrowding re-bars in the anchorage zone can be solved and the construction quality of the concrete work will be improved. But there are some problems in applying it to the NPP structures because of the restriction on the re-bar yield strength and diameter. After the performance evaluation test for the mechanical development, we can develop the new design equation of the mechanical development length in order to solve the limitation and apply it to NPP structures.

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

  • Lim, Sang-Jun;Lee, Byung-Soo
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2015.05a
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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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Performance Evaluation of Welding Method for Modular of High-Strength Reinforcing Bars to the Nuclear Power Plant Structures (원전구조물 고강도철근 모듈화를 위한 용접방법 성능평가)

  • Lim, Sang-Joon;Lee, Han-Woo;Kim, Hyeong-Seob;Bang, Chang-Joon
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2013.05a
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    • pp.278-280
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    • 2013
  • To minimize construction quantity of nuclear facility, it is required to reduce reinforcing bar amount and solve reinforcing bar concentration and for this, it is necessary to develop application 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.

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The Rebar Modulation Method in the Area of the Nuclear Power Plant Structures (원전구조물 부위별 철근모듈화 방안 연구)

  • Lee, Byung-Soo;Bang, Chang-Joon;Kim, Hun Jin;Lim, Sang-Joon;Park, Jong-Hyuk
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2013.11a
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    • pp.15-16
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    • 2013
  • Because of the complicated shape and the overcrowded arrangement of rebar, there are some problems in applying the rebar modulation for the Nuclear Power Plant Structures. In order to resolve these problems, we have been studying the rebar modulation method applying techniques of the high strength rebar for NPP Structure. 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. I will introduce this method and the future plan of the research.

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Study of application method for the Rebar Modulation of High-Strength Reinforcing Bars to the Nuclear Power Plant Structures (원전구조물 고강도철근 모듈화를 위한 적용방법 연구)

  • Lim, Sang-Joon;Lee, Byung-Soo;Bang, Chang-Joon
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2013.11a
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    • pp.17-18
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    • 2013
  • 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. This study is to introduce application method for the Rebar Modulation of High-Strength Reinforcing Bars to the Nuclear Power Plant Structures.

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Evaluation of Structural Capacity of SC Walls in Nuclear Power Plant accounting for the Area Lost to Openings (개구 저감률에 의한 원전 SC벽체의 내력 평가)

  • Chung, Chul-Hun;Jung, Raeyoung;Moon, Il Hwan;Lee, Jungwhee
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.33 no.6
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    • pp.2181-2193
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    • 2013
  • The shear wall with openings built with reinforced concrete(RC) have been elaborately studied by many researchers, whereas the steel plate concrete(SC) wall structure has not been investigated as much. Recent SC wall structures developed in Korea have been partly applied to nuclear power plant structures, although its design specification or guideline for the SC wall structure with openings has not been completed yet. This study based on the account for the area lost to openings evaluates the effects of opening on the structural capacity of the SC structure within nuclear power plant. The results obtained from the study on the area lost to openings have been compared with experimental and numerical studies.