• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2018년도 춘계 학술논문 발표대회
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• pp.99-100
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• 2018

Because of the congestion problems, the high-strength reinforcements are expected to be used in nuclear power plant structures in the near future. According to ACI 349-13, it is permitted to use the high-strength(550MPa) hooked bars in design of development length, but there is no special equation for high-strength bars. In order to reflect the anchorage capacity and behavior properties of high-strength bars with large-diameter(43 & 57mm), it is necessary to develope the new development length equation for large-size and high-strength bars.

• Nuclear Engineering and Technology
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• 제41권9호
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• pp.1157-1170
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• 2009

A variety of Generation III/III+ reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power industries around the world to solve the future energy supply shortfall. Nanofluid coolants showing an improved thermal performance are being considered as a new key technology to secure nuclear safety and economics. However, it should be noted that there is a lack of comprehensible design works to apply nanofluids to Generation III+ reactor designs. In this work, the review of accident scenarios that consider expected nanofluid mechanisms is carried out to seek detailed application spots. The Axiomatic Design (AD) theory is then applied to systemize the design of nanofluid-engineered nuclear safety systems such as Emergency Core Cooling System (ECCS) and External Reactor Vessel Cooling System (ERVCS). The various couplings between Gen-III/III+ nuclear safety features and nanofluids are investigated and they try to be reduced from the perspective of the AD in terms of prevention/mitigation of severe accidents. This study contributes to the establishment of a standard communication protocol in the design of nanofluid-engineered nuclear safety systems.

• Journal of Radiation Protection and Research
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• 제34권2호
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• pp.77-81
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• 2009

An Area Radiation Monitoring System (ARMS) ionization chamber, which had an 11.8 L active volume, was fabricated and performance-tested at KAERI. Low leakage currents, linearities at low and high dose rates were achieved from performance tests. The correlation coefficients between the ionization currents and the dose rates are 1 at high dose rate and 0.99 at low dose rate. In this study, an integration-type ARMS ionization chamber was tested over a year for an evaluation of its long-term stability at a radioisotope (RI) repository of the Young-gwang nuclear power plant. The standard deviation of dose rate of 1 day data and over a 100-days mean value were 6.2 $\mu$R/h and 2.9 $\mu$R/h, respectively. The fabricated ARMS ionization chamber showed stable performance from the results of the long-term tests. Design and performance characteristics of the fabricated ionization chamber for the ARMS from performance-tests are also addressed.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2012년도 추계 학술논문 발표대회
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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.

• 한국안전학회지
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• 제12권4호
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• pp.143-152
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• 1997

Probabilistic Safety Assessment(PSA) is an engineering analysis of the possible contributors to the risk from a nuclear power plant. It consist of three phases named as Level 1, 2 and 3. Level 1 PSA mainly focused in this paper is the phase of system analysis which includes the development of accident scenarios and the frequency estimation of each scenario. It covers also the system reliability analysis, component data analysis, and human reliability analysis. PSA have become a standard tool in safety evaluation of nuclear power plants. The main benefit of PSA is to provide insights into plant design, performance and environmental impacts, including the identification of dominant risk contributors and the comparison of options for reducing risk.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2013년도 춘계 학술논문 발표대회
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• pp.273-275
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• 2013

If the mechanical development is 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 yield strength and diameter of the re-bar. 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.

• 한국건설관리학회논문집
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• 제18권1호
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• pp.48-57
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• 2017

1971년 우리나라 최초의 원자력발전소인 고리 1호기가 착공되어 2015년 현재 24기가 가동 중에 있으며 4기가 건설 중으로 약 40여 년간의 원자력발전소 건설 역사 동안 원전 건설의 성공적인 시공을 위한 CSFs 도출에 관한 연구는 아주 미흡한 실정이다. 본 연구에서는 시공단계에서 원전 건설의 성공적인 시공을 위한 CSFs를 도출하기 위하여 기존 연구에서 제안된 원전 및 일반 건설의 성공요인과 고찰한 원전 건설의 시공요인을 바탕으로 원전 전문가와 포커스 그룹 인터뷰를 실시하여 원전 건설의 성공적인 시공을 위한 CSFs를 도출하였다. 포커스 그룹 인터뷰 결과의 검증을 위하여 현재 원전 건설 프로젝트에 참여하고 있는6 14명의 실무 전문가들의 설문조사를 통해 도출한 CSFs의 유용성을 검증하였다. 설문 결과 분석을 통해 합리적인 공사비산정기준 수립, 원전 건설경험 인력 관리시스템 구축 및 활용, 경쟁력 있는 우수 협력업체 발굴 및 육성 방안 마련 및 검사 절차 개선 등으로 작업 대기시간의 최소화 방안 등에 대해 우선 검토 및 개선이 이루어져야 함을 도출 하였다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2008년도 학술대회 논문집 정보 및 제어부문
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• pp.515-517
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• 2008

현재 가동 중인 원자적발전소 계측제어설비의 전원공급기를 살펴보면 인버터 또는 별도의 교류를 입력전원으로 사용한다. 직류 전원공급기들은 설비의 중요도예 따라 이중화로 구성된 설비도 있고 그렇지 않은 기기나 설비도 있다. 이중화로 구성된 전원공급기라 해도 교류 입력전원이 동일하다면 교류 입력이 상실될 때 이중화로 구성된 직류전원도 상실되어 관련계통의 가동이 정지된다. 이러한 문제점을 해결하기 위해서는 각기 다른 교류입력전원으로 동작되는 이중화전원공급기로 구성되는 것이 가장 바람직하다. 본 연구개발의 목적은 두 종의 설비에 소요되는 3종의 직류전원 공급기를 원자력 안정성등급으로 국산화하는 연구이다. 기존 제품들은 3종 모두 리니어 방식의 제품이지만, 방사선감시 계통 현장제어기의 5V로직 전원공급기와 공정제어계통 전원공급자는 전력변환효율이 높고 소형, 정량화가 가능한 SMPS(Switched Mode Power Supply) 방식으로 개발하였다. 방사선감시계통 현장제어기의 PCA(Printed Circuit Assembly) 저전압공급기는 다양한 종류의 출력전압과 저 전류형이므로 안정성 면에서 동일한 형식의 리니어 방식으로 개발하였으며 3종류 모두 출력용량을 20% 이상 향상시켰다. 또한, 논문을 통해 SMPS 방식의 전원공급기의 핵심 부품인 Control Module을 Hybrid IC형으로 자체 설계하여 성능이 우수한 제품을 지속적으로 생산할 수 있는 기틀을 마련하고자 한다.

• 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.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2013년도 춘계 학술논문 발표대회
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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.