초록 ▼

ㅇ 원전 안전성 강화에 따른 중대사고 환경에서의 기기생존성 평가기술 개발
□ 2022년 승인 예정인 원전 사고관리계획서 대응 목표
□ 사고관리계획서 승인 이후 우선적으로 필요한 시험 대상 및 환경 조사
(사고관리계획서 작성 조직과의 교류 수행)
ㅇ 중대사고 기기생존성 평가기술 관련 평가방법론 및 실증 시험설비 개발
□ 수소연소 동반 중대사고 환경 특정(900K, 109 psig) 및 관련 시험설비 개발
□ 실제와 유사한 환경 조성을 위한 빠른 승온/승압 속도 확보에 중점을 둠
(목표: 900K

ㅇ 원전 안전성 강화에 따른 중대사고 환경에서의 기기생존성 평가기술 개발
□ 2022년 승인 예정인 원전 사고관리계획서 대응 목표
□ 사고관리계획서 승인 이후 우선적으로 필요한 시험 대상 및 환경 조사
(사고관리계획서 작성 조직과의 교류 수행)
ㅇ 중대사고 기기생존성 평가기술 관련 평가방법론 및 실증 시험설비 개발
□ 수소연소 동반 중대사고 환경 특정(900K, 109 psig) 및 관련 시험설비 개발
□ 실제와 유사한 환경 조성을 위한 빠른 승온/승압 속도 확보에 중점을 둠
(목표: 900K / 60초, 실적: 900K / 15초)
ㅇ 소재 단위(비금속재료)의 기기생존성 영향성 분석
□ 열화거동 평가 및 원전사고 환경요소가 기기생존성에 미치는 영향 분석
□ 소재 단위의 기기생존성 평가방법론 제시
ㅇ 중대사고 환경 유로기기 성능평가를 위한 유량계측 시험 및 해석 방법론 구축

(출처 : 요약 3p)

Abstract ▼

1. Objective and significance of research
□ Purpose of R&D
□ Development of equipment survivability evaluation technology for severe accidents mitigation equipment of nuclear power plants
□ Develop technology for evaluating the survival of severe accidents to improve the safety of nuclear p

1. Objective and significance of research
□ Purpose of R&D
□ Development of equipment survivability evaluation technology for severe accidents mitigation equipment of nuclear power plants
□ Develop technology for evaluating the survival of severe accidents to improve the safety of nuclear power plants
□ Establishment of equipment survival evaluation facility for severe accidents
□ Respond to nuclear power plant regulations through the established equipment survivability evaluation system for severe accidents and carried out consignment tasks in the industry
□ Contributing to overseas export of domestic nuclear power plants through the leading development of equipment survival evaluation technology for severe accidents

□ Necessity of R&D
□ Reinforcement of regulations related to severe accidents in response to requests for submission of nuclear power plant accident management plans
□ Establishment of accident management plan for all nuclear power plants in Korea
□ In case of a severe accident accompanied by a hydrogen explosion through the accident management plan, a reasonable guarantee plan for the safety of nuclear power plants will be required.
□ The safety-related technology of nuclear power plants follows strict and conservative regulatory control, and the establishment of an accident management plan directly exerts a direct force on the development and acquisition of related technologies.
□ Trends in demand for domestic serious accident proof tests
□ As the accident management plan is enacted, the demand for equipment survivability evaluation technology for severe accidents is expected to increase.
□ A total of 28 nuclear power plants under construction and operation in Korea
□ There have been no cases in Korea for empirical tests related to device survivability in severe accidents.
□ There has been a demand for a serious accident demonstration test for I&C-series devices applied to Shin-Kori Units 5 & 6, and the case is currently being conducted by leading overseas organizations due to the lack of domestic demonstration test technology.
□ The system for demonstrating the survival of serious accidents based on tests has not been established in leading countries, and if related technologie is developed in advance, it can be used to prove the safety excellence of domestic nuclear power plants compared to overseas nuclear power plants.
□ Through this, it can be expected to contribute to the safety of the people and strengthen the competitiveness of the Korean nuclear power plant (APR1400), whichis planning to export.

2. Contents and scope of research
□ Selecting a method for evaluating the survivability of each target device and environment for a severe accident demonstration test
□ Survey of KHNP, KEPCO technology personnel in charge of serious accidents and manufacturers of safety-grade nuclear equipment
□ Development of a combination evaluation methodology for empirical tests for I&C-series devices, tests and analysis for machinery and special devices

□ Development of a methodology for evaluating the survival of severe accidents
□ Investigate and reflect the equipment survivability evaluation procedure established by nuclear power plant operators and designers
□ Verification and supplementation of device survivability evaluation procedures based on empirical tests
□ Develop a combination evaluation methodology of test and analysis based on analysis of the device viability impact of material units (non-metallic materials) and thermal analysis
□ Analysis of dynamic characteristics for optimal design of nuclear fire protection lab (substitute means for severe accidents)

□ Development of equipment survival test facility for severe accidents
□ Applying Highly Challenging Environments reflecting severe accident analysis suggested by nuclear power plant operators and designers (Severe accident environment with hydrogen combustion, 109 psig, 900K)
□ Development of technology for securing temperature increase/pressure speed to create an environment similar to real life (target: 900K, 109 psig / 60 seconds, performance: 900K, 80 psig / 15 seconds)
□ Establishment of flow measurement test and analysis methodology for the performance evaluation of fluid path equipment in a severe accident environment
□ Analysis of high pressure environmental flow measurement method through evaluation of major performance indicators of orifice flow meter
□ Study on the design, manufacture, test and test-based analysis methodology of test facilities for understanding flowmeter characteristics
□ Certified by Korea Nuclear Safety Foundation for analysis methodology (high pressure gas flow measurement analysis methodology)
3. R&D achievement
4. Plan to utilize R&D achievements
□ Demonstration test of major accidents for domestic nuclear power plants
□ Development of the first severe accident proof test facility in Korea
□ Use for solving difficulties of nuclear power plant equipment manufacturers through private enterprise consignment

□ Development of equipment for severe accidents and response to difficulties of nuclear power plant operators
□ Used for verification and development of equipment to respond to severe accidents in nuclear power plants during operation
□ Used to respond to difficulties related to severe accidents of nuclear power plant operators
□ Support for industries related to nuclear power plants in the Southeast region
□ Development of Korea's best nuclear equipment verification technology centered on the Busan Mechanical Technology Research Center of Korea Institute of Machinery and Materials
□ Dissemination of extreme environment simulation technology for Southeastern shipbuilding/offshore/plant and defense industries

(출처 : SUMMARY 9p)

목차 Contents

• 표지 ... 1
• 제 출 문 ... 2
• 단계 보고서 ... 3
• 요 약 문 ... 4
• SUMMARY ... 9
• CONTENTS ... 13
• 목차 ... 14
• 제1장 연구개발과제의 개요 ... 15
• 1. 연구개발의 목적 ... 15
• 2. 연구개발의 필요성 및 범위 ... 15
• 제2장 국내외 기술개발 현황 ... 18
• 제3장 연구개발수행 내용 및 결과 ... 23
• 1. 중대사고 기기생존성 종합영향 평가방법론 개발 ... 23
• 2. 중대사고 기기생존성 평가 기술기준 및 요건 분석 ... 26
• 3. 중대사고 기기생존성 실증시험 설비 구축 ... 32
• 4. 비금속소재 열화거동 기반 중대사고 기기생존성 평가방법론 개발 ... 44
• 5. 중대사고 대체수단 최적화 설계방안 ... 55
• 6. 중대사고 대비 유로기기 유량 특성 평가 기술 개발 ... 57
• 제4장 목표달성도 및 관련분야에의 기여도 ... 59
• 1. 목표달성도 종합 ... 59
• 2. 관련분야에의 기여 ... 65
• 제5장 연구개발성과의 활용계획 ... 66
• 제6장 연구시설·장비 현황 ... 67
• 제7장 참고 문헌 ... 68
• 끝페이지 ... 69