Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system

논문상세정보
' Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • 응용 물리
  • Safety analysis
  • Heat pipe cooled reactor
  • Small nuclear reactor system
  • Thermal-hydraulic characteristics
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
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