Fracture Toughness Behavior of Zircaloy-4 in the Form of Fuel Cladding Tubing in Nuclear Reactors.POMPES PAR TRANSITIONS MULTIPLES

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" Fracture Toughness Behavior of Zircaloy-4 in the Form of Fuel Cladding Tubing in Nuclear Reactors.POMPES PAR TRANSITIONS MULTIPLES "

Document Type	:	Latin Dissertation
Language of Document	:	English
Record Number	:	153576
Doc. No	:	ET25368
Main Entry	:	Yongli REN
Title Proper	:	Fracture Toughness Behavior of Zircaloy-4 in the Form of Fuel Cladding Tubing in Nuclear Reactors.POMPES PAR TRANSITIONS MULTIPLES
Note	:	This document is digital این مدرک بصورت الکترونیکی می باشد
Abstract	:	Based on previous work, a modified VEC technique has been developed in this study.This technique has been proven, through the HCP based Ti3A12.W tubing, to be reliablefor fracture toughness measurement of thin-walled tubes. The average critical J integralvalue of unirradiated Zircaloy-4 cladding is hence determined to be 82.6 kN/m,.
Subject	:	Electericl tess
	:	برق
electronic file name	:	TL49620.pdf
Title and statement of responsibility and	:	Fracture Toughness Behavior of Zircaloy-4 in the Form of Fuel Cladding Tubing in Nuclear Reactors.POMPES PAR TRANSITIONS MULTIPLES [Thesis]