초록 ▼

ㅇ 원전의 대용량화 및 평가기술의 한계로 설계기준사고 및 중대사고에서의 건전성 평가 기술 개발이 요구되고 있으나, 국내의 경우 평가기술이 미비 혹은 전무한 상태로 연구개발이 필요한 분야임
ㅇ 설계기준사고 및 중대사고 환경에서 원전기기의 건전성을 평가하기 위한 설비 개선 및 평가 방법론에 대한 기술개발 수행
- 열유동 특성 및 검증설비 개선을 통해 원전기기 설계기준사고 환경에서 대형기기에 대한 검증이 가능한 설비의 시험초기 급변 환경구간 모사 기술 개발(기존대비 80% 이상 단축)
- 화학살수 설비 교체 및 개선을 통

ㅇ 원전의 대용량화 및 평가기술의 한계로 설계기준사고 및 중대사고에서의 건전성 평가 기술 개발이 요구되고 있으나, 국내의 경우 평가기술이 미비 혹은 전무한 상태로 연구개발이 필요한 분야임
ㅇ 설계기준사고 및 중대사고 환경에서 원전기기의 건전성을 평가하기 위한 설비 개선 및 평가 방법론에 대한 기술개발 수행
- 열유동 특성 및 검증설비 개선을 통해 원전기기 설계기준사고 환경에서 대형기기에 대한 검증이 가능한 설비의 시험초기 급변 환경구간 모사 기술 개발(기존대비 80% 이상 단축)
- 화학살수 설비 교체 및 개선을 통해 대용량 화학살수 기술확보(0.72 gpm/ft²)
- 중대사고 환경에서의 기기생존성 평가를 위한 시험설비 설계/제작 및 열/방사선 환경을 고려한 부품소재 건전성 평가 방법론 개발

( 출처 : 최종보고서 요약 3p )

Abstract ▼

1. Objective and significance of research
□ Objective
○ Development of Emerging Core Technique of Equipment Qualification on Design Based Events and Severe Accidents of NPPs
- Development of type testing technique in design basis accident environment
- Development of evaluation technique

1. Objective and significance of research
□ Objective
○ Development of Emerging Core Technique of Equipment Qualification on Design Based Events and Severe Accidents of NPPs
- Development of type testing technique in design basis accident environment
- Development of evaluation technique of non-metallic materials in severe accident environment

□ Significance of research
○ It is required to evaluate the integrity of class 1E safety equipment in design basis accident environment to secure the safety of nuclear power plant.
- Qualification requirements on safety equipment of class 1E in design basis accident environment : IEEE 323, KEPIC END 1100, 10 CFR 50.49, Reg. Guide 1.89, NSSC notification 2012-178 and 2013-8

○ Market increasing and limitation of assessment technique in design basis accident environment
- An increase in demand : qualification market of large capacity equipment
· Domestic market of large-scale equipment : Nuclear power plants under construction after Shin kori 3 &4 (Shin kori 5 & 6, shin uljin 1 & 2 and BNPP (UAE))
· Current status of construction of nuclear power plant : 71 plants in 15 countries(China 28 plants, russia 10 plants, korea 5 plants, US 5 plants.
· Qualification technique in design basis accident is remain at 10 years ago. Especially, it is necessary to develop large-scale chemical spray technique and simulation technology of initial state in design basis accident environment.
· The failure to respond to the demand for the qualification of the equipment can lead to dependence on foreign countries.

○ Mega trend of equipment for nuclear power plant filed : Qualification technique in severe accident environment
- Fukushima Daiichi Nuclear Plant: 2011.03.11. 14m tsunami
- Fort Calhoun Nuclear Plant: 2011.06.06. Over 500 year Missouri River Flooding
- Importance of qualification technique in severe accident environment.
· NSSC decided to apply the Fukushima action plan requirements including prevention and mitigation of severe accident to new construction nuclear power plants. Regulatory activities are being carried out to reflect the requirements before the operation permission and commercial operation.
· The current class 1E safety equipment in service do not have a qualification method for survivability in severe accident environment.

○ The qualification of equipment survivability of class 1E safety equipment in construction plants such as Shin kori 5 & 6 depends entirely on foreign countries due to lack of qualification technique.
- Considering the permission for operation of new construction nuclear power plant, research of equipment survivability qualification technique is required.

2. Contents and scope of research
□ Development of Emerging Core Technique of Equipment Qualification on Design Based Events and Severe Accidents of NPPs.
○ Development of type testing technique in design basis accident environment.
- Development of simulation technique of initial rapidly changing environment of design basis accident. (less than 50%)
· Development of simulation technique can qualify in rapidly changing environment(temperature and pressure) for large-scale equipment.
· The rapidly changing region in LOCA tesing decreased for less than 80% compared to existing technology.
- Development of chemical spray technique in testing with design basis accident environment.
· Achievement of test capacity to respond concept of new reactor though replacement and improvement of chemical spraying facilities.
· Large capacity chemical spray technique is developed to install and improve the new cooling system (0.62 gpm/ft²)

○ Development of evaluation technique of non-metallic materials in severe accident environment
- The qualification equipment for equipment survivability was designed and developed.(peak temperature with higher than 627 deg.C)
· The equipment can assess the equipment survivability in hydrogen burn environment(peak temperature with 627 deg.C) was designed and manufactured.
- Develop and performed of evaluation degradation technology to non-metallic materials in severe accident environment with temperature and radiation.
· Perform the degradation test on VITON that major non-metallic material in prevention and mitigation equipment such as ERDV (Emergency Reactor Depressurization Valve)
· Degradation test was performed in normal operation condition and severe accident environment considering thermal and irradiation condition.

4. Plan to utilize R&D achievements
□ Technical support the design and qualification of nuclear equipment
○ Application to design and qualification of safety-related equipment for severe accident in 3.5 generation nuclear power plants.
○ Leading the world in nuclear equipment design/qualification and engineering.
○ Trouble shooting through technical support to manufacturer of nuclear equipment.

□ Establishment of infrastructure for export hub of nuclear equipment
○ Fostering high value-added product manufacturers.
- To ensure reliability by designing / manufacturing / qualification to exportation through local manufacturing.
○ Establishment and operation of equipment qualification center
- The result of feasibility study including economic efficiency and feasibility using regional input-output table: KRW 74.0 billion in production inducement effect (KRW 45.9 billon in busan region), KRW 27.8 billion in value added effect (18.6 billion in busan region), 638 people in employment inducement effect (469 people in busan region)
- The economic earning can be expected more than KRW 51 billion over the next 20 years by estimating the market of qualification of nuclear equipment.

( 출처 : SUMMARY 8p )

목차 Contents

• 표지 ... 1
• 제 출 문 ... 2
• 최종보고서 ... 3
• 요 약 문 ... 4
• SUMMARY ... 8
• CONTENTS ... 13
• 목차 ... 14
• 제1장 연구개발과제의 개요 ... 15
• 1. 연구개발의 목적 ... 15
• 2. 연구개발의 필요성 및 범위 ... 15
• 제2장 국내외 기술개발 현황 ... 17
• 1. 국내 기술개발 현황 ... 17
• 2. 국외 기술개발 현황 ... 19
• 제3장 연구개발수행 내용 및 결과 ... 20
• 1. 설계기준 사고 및 중대사고 기술요건 조사 결과 ... 20
• 2. 원전기기 설계기준사고 모사 시험기술 개발 ... 21
• 3. 원전 중대사고 환경 부품소재 건전성 평가 기술 개발 ... 29
• 제4장 목표달성도 및 관련분야에의 기여도 ... 48
• 1. 목표달성도 종합 ... 48
• 2. 관련분야에의 기여 ... 52
• 제5장 연구개발성과의 활용계획 ... 54
• 제6장 연구시설·장비 현황 ... 55
• 제7장 참고 문헌 ... 56
• 끝페이지 ... 58