Zirconium-Based Cladding Coating Technique for Oxidation, Corrosion and Embrittlement Reduction at High-Temperature: An Overview von Sagiroun, Mamoun I. A., Xinrong, Cao

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Study and assessment of (FeCrAl) and (SiC) as candidate materials for accident tolerant fuel cladding in LWRs von Sagiroun, Mamoun I A, Xinrong, Cao, Ayoub, Anuor A T

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Radionuclide migration in fresh water from nuclear power plant liquid effluent discharged: (Hypothetical case study) von Ayoub, Anuor AT, Song, Yushou, Sagiroun, Mamoun IA, Omhahmed

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Radiological hazard assessment for human from nuclear power plant effluent released under normal operation scenario (hypothetical case study) von Ayoub, Anuor AT, Song, Yushou, Sagiroun, Mamoun IA

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A Review of Development of Zirconium Alloys as a Fuel Cladding Material and its Oxidation Behavior at High-Temperature Steam von Cao, Xin Rong, Njoroge, John N., Helal, Wasim M.K., Sagiroun, Mamoun I.A.

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