Thermal Hydraulic Analysis of Core Flow Bypass in a Typical Research Reactor

Said M.A. Ibrahim Salah El-Din El-Morshedy Abdelfatah Abdelmaksoud 2019년

논문상세정보

인용/피인용

논문영향력 요약
동일주제 총논문수	논문피인용 총횟수	주제별 논문영향력의 평균
주제	Core flow bypass MTR reactors Thermalehydraulics
5	0	0.0%

논문영향력
주제		주제별 논문수	주제별 논문영향력
주제어	Core flow bypass	2	0.0%
	MTR reactors	2	0.0%
	Thermalehydraulics	1	0.0%
계		5	0.0%
* 다른 주제어 보유 논문에서 피인용된 횟수

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