초록 ▼

$\circ$운전원을 포함한 원전계측제어시스템의 정량적 안전성 평가 기술 개발
$\circ$운전원을 포함한 평가모델 만들 수 있는 새로운 확률론적 안전성 평가방법인 일반적인 게이트를 갖는 신뢰도 그래프라는 방법론을 개발
$\circ$원전계측제어시스템의 정보흐름에 대한 자료 수집, 운전원의 단순실수에 대한 분석, 운전원의 지식과 정보처리 능력 사이의 상관관계 평가, 운전원의 작업부하와 정보처리능력 사이의 상관관계 평가등을 통하여 발전소 운전원을 분석하여 운전원의 행

$\circ$운전원을 포함한 원전계측제어시스템의 정량적 안전성 평가 기술 개발
$\circ$운전원을 포함한 평가모델 만들 수 있는 새로운 확률론적 안전성 평가방법인 일반적인 게이트를 갖는 신뢰도 그래프라는 방법론을 개발
$\circ$원전계측제어시스템의 정보흐름에 대한 자료 수집, 운전원의 단순실수에 대한 분석, 운전원의 지식과 정보처리 능력 사이의 상관관계 평가, 운전원의 작업부하와 정보처리능력 사이의 상관관계 평가등을 통하여 발전소 운전원을 분석하여 운전원의 행위묘사를 위한 인지모델 및 정보처리 모델을 개발
$\circ$개발된 기술을 이용하여 현 시스템을 평가
$\circ$본 연구에서 개발된 평가 모델들을 사용하여 인간기계연계, 운전지원시스템, 발전소에 대한 정량적 평가를 수행
$\circ$평가 결과를 기반으로 안전성을 극대화 할 수 있는 새로운 원전계측제어시스템의 패러다임을 제안
$\circ$운전원을 포함한 발전소의 안전성을 평가한 결과를 기반으로 운전원의 인지과정을 지원해줄 수 있는 운전원 중심적인 새로운 설계 패러다임을 제안

Abstract ▼

The possibility of human failure or human error has a significant impact on the safety or reliability of nuclear power plants (NPPs). In fact, most analysis results of NPP accidents including Chernobyl and TMI-2 accidents indicate that human error is one of the main causes of them. In an analysis of

The possibility of human failure or human error has a significant impact on the safety or reliability of nuclear power plants (NPPs). In fact, most analysis results of NPP accidents including Chernobyl and TMI-2 accidents indicate that human error is one of the main causes of them. In an analysis of the abstracts from 180 significant events reported to have occurred in the United States, it was found that 48% of the incidents were attributed to human factor failures. The main control room (MCR) operators in an NPP have a supervisory role for information gathering, planning, and decision making. Such operation tasks in MCRs are very complex and mentally taxing activities. In such environment, human error has a significant impact on safety. Moreover, as digitalized instrumentation and control (I&C) systems have been adopted in NPPs, the impact of human errors have become more important. Therefore, the quantitative safety analysis method considering human operator is necessary for more reliable evaluation of system's safety, but there is no developed method even in advanced countries. The safety assessment is still performing using qualitative methods. The technique, 'quantitative safety assessment method for NPP I&C systems including human operators' which is the title of this project, will be more flexible to confront with environment changes and be more useful for evaluating digital I&C systems. The fundamental technique for safety assessment is the modeling method to make evaluation model. Though the fault tree analysis (FTA) is most popular and widely used probabilistic safety assessment (PSA) method, it has several limits to make a model including human operators. Thus, new PSA method was developed, that is the reliability graph with general gates (RGGG). Then, various analyses about human operator were performed to make a model considering human. Data of information flow in I&C systems were collected, simple errors of operators were analyzed, the relationship between operators' knowledge and information handling capacity was investigated, and the relationship between workload and information handling capacity was also investigated. Through these research we developed the information process model and cognitive model for describing operators' actions. Then, for next step, the quantitative evaluations of human-machine interface (HMI), operator support systems, and an NPP were performed. The results said operators is very sensitive for NPP safety, so we suggested new design paradigm for safer NPP I&C systems by analyzing operators' cognitive process and developed a system for advanced main control rooms, that is the integrated decision support system to aid the cognitive activities of operators (INDESCO). Finally, suggested system was evaluated using suggested evaluation techniques resulting in reduced human errors and increased operators' performance.

목차 Contents

• 제 1 장 연구개발과제의 개요...8
• 제 1 절 연구목표...8
• 제 2 절 연구개발의 필요성...11
• 제 2 장 국내외 기술개발 현황...15
• 제 1 절 국내외 타기관의 연구개발 실적...15
• 제 2 절 본 연구실의 연구개발 실적...18
• 제 3 절 현 기술상태의 취약성...18
• 제 3 장 연구개발수행 내용 및 결과...20
• 제 1 절 전체적인 연구 결과...20
• 제 2 절 연구개발 수행 내용...21
• 제 3 절 실적 및 구축된 장비...87
• 제 4 장 목표달성도...91
• 제 5 장 연구개발결과의 활용계획...95
• 제 1 절 연구결과(개발기술)의 활용계획 및 활용가능성...95
• 제 2 절 앞으로의 전망...96