Radiation Effects on the Metallurgical Fracture Parameters and Fracture Toughness of Pressure Vessel Steels PDF Download
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Author: DR. Ireland Publisher: ISBN: Category : Bituminous materials Languages : en Pages : 20
Book Description
The effect of radiation on tensile properties, notch bend properties, and fracture toughness was determined on A212B steel from the Pathfinder reactor surveillance program and on A533B steel from the U.S. AEC Heavy Section Technology program. Impact tests were performed on an instrumented Charpy machine which provided load-deflection data in addition to energy absorption data. Valid fracture toughness values were obtained from precracked Charpy specimens.
Author: DR. Ireland Publisher: ISBN: Category : Bituminous materials Languages : en Pages : 20
Book Description
The effect of radiation on tensile properties, notch bend properties, and fracture toughness was determined on A212B steel from the Pathfinder reactor surveillance program and on A533B steel from the U.S. AEC Heavy Section Technology program. Impact tests were performed on an instrumented Charpy machine which provided load-deflection data in addition to energy absorption data. Valid fracture toughness values were obtained from precracked Charpy specimens.
Author: P. Soulat Publisher: ISBN: Category : Elastic-plastic fracture mechanics Languages : en Pages : 22
Book Description
Irradiation experiments were conducted in order to determine the effect of radiation damage on the elastic-plastic ductile fracture toughness of pressure vessel steels. Curves for the J-integral versus crack growth resistance (?a) were established on specimens taken out of two nuclear reactor pressure vessel steels before and after neutron irradiation at 290°C to a fluence of 3.1019 n/cm2 (work function energy E > 1 MeV). The J-?a tests were performed at room temperature (25°C) and service temperature (290°C). The main results obtained are as follows:.
Author: Nikolaĭ Nikolaevich Alekseenko Publisher: ISBN: Category : Technology & Engineering Languages : en Pages : 304
Book Description
This book describes the current state of knowledge about pressure vessel material selection, fabrication (including welding), the changes in properties in service, and response to high-temperature annealing. In contrast to the bad reports of inadequate attention to reactor safety in the former Soviet Union, this book shows that the question of pressure vessel performance has received proper attention and a strong scientific base underlies the assessment of vessel life. This book should be read by reactor designers and operators and their scientific colleagues throughout the world.
Author: DR. Ireland
Author: DR. Ireland
Author: Lendell E. Steele
Author: P. Soulat
Author: D. S. Gelles
Author: John Moteff
Author: Todd R. Allen
Author: A. L. Bement
Author: Nikolaĭ Nikolaevich Alekseenko
Author: L. P. Trudeau
Author: