Flow Characteristics Evaluation in Reactor Coolant System for Full System Decontamination of Kori-1 Nuclear Power Plant

논문상세정보
' Flow Characteristics Evaluation in Reactor Coolant System for Full System Decontamination of Kori-1 Nuclear Power Plant' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • RHR pump
  • Range of system decontamination
  • System decontamination
  • 계통제염
  • 계통제염범위
  • 잔열제거펌프
  • Kori-1 nuclear power plant
  • 고리1호기
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