Proposal of New Oβ Oxidation Criterion for New Types of Zr1Nb Alloys of Fuel Claddings Martin Négyesi Department of Materials, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague,

First Page		Document Content
Date: 2012-07-16 15:39:06 Transition metals Zirconium alloy Zirconium Embrittlement Vanadium Hydrogen Iron Nuclear fuel Oxide Chemistry Matter Chemical elements		Proposal of New Oβ Oxidation Criterion for New Types of Zr1Nb Alloys of Fuel Claddings Martin Négyesi Department of Materials, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Add to Reading List Source URL: www.djs.si Download Document from Source Website File Size: 347,00 KB Share Document on Facebook

	2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju • Jeju Island, Korea Pre-transition Oxide Characterization of Zirconium Alloy Cladding on the Zinc Injection and the Hig DocID: 1v6u3 - View Document
	EPJ Nuclear Sci. Technol. 2, ) © C. Giovedi et al., published by EDP Sciences, 2016 DOI: epjnNuclear Sciences DocID: 1rekx - View Document
	Hyperfine Interact:199–204 DOIs10751A Mössbauer investigation of zirconium distribution and diffusion in ball milled nanocrystalline iron powders M. D. Martin · Y. Fahmy · A. M. Khasa DocID: 1p8jP - View Document
	EPJ Nuclear Sci. Technol. 2, ) © J. Sercombe et al., published by EDP Sciences, 2016 DOI: epjnNuclear Sciences DocID: 1oh6e - View Document
	Hydride formation in cladding materials studied via in-situ environmental heating transmission electron microscopy S. Rajasekhara, K. Hattar, V. Tikare, R. Dingreville, and B. G. Clark Sandia National Laboratories, Albuq DocID: 1nOjf - View Document