Some Observations of the Intergranular Corrosion of Irradiated Type 304 Stainless Steel

Some Observations of the Intergranular Corrosion of Irradiated Type 304 Stainless Steel PDF Author: E. L. Long (Jr.)
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 38

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Some Observations of the Intergranular Corrosion of Irradiated Type 304 Stainless Steel

Some Observations of the Intergranular Corrosion of Irradiated Type 304 Stainless Steel PDF Author: E. L. Long (Jr.)
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 38

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Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels

Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels PDF Author: HM. Chung
Publisher:
ISBN:
Category : Auger electron spectroscopy
Languages : en
Pages : 19

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Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control blade sheath after irradiation up to 2.5x1021 n•cm-2 (E>1 MeV) in boiling water reactors (BWRs). The susceptibility of the HP absorber tubes to intergranular stress corrosion cracking (IGSCC) was higher than that of the CP absorber tubes or the CP control blade sheath. IGSCC susceptibilities of the BWR components could not be correlated with segregation of impurities on grain boundaries. However, for comparable fluence levels, the susceptibilities could be correlated to concentrations of Cr on grain-boundaries.

Intergranular Corrosion of Stainless Alloys

Intergranular Corrosion of Stainless Alloys PDF Author: R. F. Steigerwald
Publisher: ASTM International
ISBN: 9780803103788
Category : Science
Languages : en
Pages : 270

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Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels

Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 19

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Book Description
Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control blade sheath after irradiation up to 2.5 [times] 10[sup 2l] n[center dot]cm[sup [minus]2] (E> l MeV) in boiling water reactors (BWRs). The susceptibility of the HP absorber tubes to intergranular stress corrosion cracking (IGSCC) was higher than that of the CP absorber tubes or the CP control blade sheath. IGSCC susceptibilities of the BWR components could not be correlated to segregation impurities on grain boundaries. However for comparable fluence levels, Cr on grain-boundaries.

Effects of Irradiation on Intergranular Stress Corrosion Cracking of Type 304 Stainless Steel

Effects of Irradiation on Intergranular Stress Corrosion Cracking of Type 304 Stainless Steel PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 11

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 852

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Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1368

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Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory

Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 304

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Intergranular Corrosion of Nonsensitized Austentic Stainless Steels

Intergranular Corrosion of Nonsensitized Austentic Stainless Steels PDF Author: J. S. Armijo
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 60

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Fundamentals of Radiation Materials Science

Fundamentals of Radiation Materials Science PDF Author: GARY S. WAS
Publisher: Springer
ISBN: 1493934384
Category : Technology & Engineering
Languages : en
Pages : 1014

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Book Description
The revised second edition of this established text offers readers a significantly expanded introduction to the effects of radiation on metals and alloys. It describes the various processes that occur when energetic particles strike a solid, inducing changes to the physical and mechanical properties of the material. Specifically it covers particle interaction with the metals and alloys used in nuclear reactor cores and hence subject to intense radiation fields. It describes the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys. Updated throughout, some major enhancements for the new edition include improved treatment of low- and intermediate-energy elastic collisions and stopping power, expanded sections on molecular dynamics and kinetic Monte Carlo methodologies describing collision cascade evolution, new treatment of the multi-frequency model of diffusion, numerous examples of RIS in austenitic and ferritic-martensitic alloys, expanded treatment of in-cascade defect clustering, cluster evolution, and cluster mobility, new discussion of void behavior near grain boundaries, a new section on ion beam assisted deposition, and reorganization of hardening, creep and fracture of irradiated materials (Chaps 12-14) to provide a smoother and more integrated transition between the topics. The book also contains two new chapters. Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking. Chapter 16 extends this treatment and considers the effects of irradiation on corrosion and environmentally assisted corrosion, including the effects of irradiation on water chemistry and the mechanisms of irradiation-induced stress corrosion cracking. The book maintains the previous style, concepts are developed systematically and quantitatively, supported by worked examples, references for further reading and end-of-chapter problem sets. Aimed primarily at students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals. Reviews of the first edition: "...nomenclature, problems and separate bibliography at the end of each chapter allow to the reader to reach a straightforward understanding of the subject, part by part. ... this book is very pleasant to read, well documented and can be seen as a very good introduction to the effects of irradiation on matter, or as a good references compilation for experimented readers." - Pauly Nicolas, Physicalia Magazine, Vol. 30 (1), 2008 “The text provides enough fundamental material to explain the science and theory behind radiation effects in solids, but is also written at a high enough level to be useful for professional scientists. Its organization suits a graduate level materials or nuclear science course... the text was written by a noted expert and active researcher in the field of radiation effects in metals, the selection and organization of the material is excellent... may well become a necessary reference for graduate students and researchers in radiation materials science.” - L.M. Dougherty, 07/11/2008, JOM, the Member Journal of The Minerals, Metals and Materials Society.