Author: HR. Peters
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 12
Book Description
In the analysis of the post-transition corrosion regime of Zircaloys in a water environment it has typically been assumed that the cycles occurring after the first cycle (pretransition) could be approximated by a constant rate. Recently, a long-term testing of Zircaloy-4 has shown this assumption to be nonconservative. Post-transition rates are seen to increase with increasing weight gain or time until a steady-state post-transition rate is achieved. The corrosion of Zircaloy-4 in a water environment is, therefore, now seen to have a transitory regime in addition to the pretransition and steady-state post-transition regimes. The mathematical description of this transitory regime is shown to fit the following: corrosion rate, R = A . ?W + B, which results in a general equation for weight gain during the transitory regime of ?W = (B/A) . (eAt - 1). This formulation provides a more accurate description of long-term Zircaloy-4 corrosion for use in engineering design than assuming post-transition kinetics based on a linear fit to the cyclic regime following the first cycle.
Improved Characterization of Aqueous Corrosion Kinetics of Zircaloy-4
Author: HR. Peters
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 12
Book Description
In the analysis of the post-transition corrosion regime of Zircaloys in a water environment it has typically been assumed that the cycles occurring after the first cycle (pretransition) could be approximated by a constant rate. Recently, a long-term testing of Zircaloy-4 has shown this assumption to be nonconservative. Post-transition rates are seen to increase with increasing weight gain or time until a steady-state post-transition rate is achieved. The corrosion of Zircaloy-4 in a water environment is, therefore, now seen to have a transitory regime in addition to the pretransition and steady-state post-transition regimes. The mathematical description of this transitory regime is shown to fit the following: corrosion rate, R = A . ?W + B, which results in a general equation for weight gain during the transitory regime of ?W = (B/A) . (eAt - 1). This formulation provides a more accurate description of long-term Zircaloy-4 corrosion for use in engineering design than assuming post-transition kinetics based on a linear fit to the cyclic regime following the first cycle.
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 12
Book Description
In the analysis of the post-transition corrosion regime of Zircaloys in a water environment it has typically been assumed that the cycles occurring after the first cycle (pretransition) could be approximated by a constant rate. Recently, a long-term testing of Zircaloy-4 has shown this assumption to be nonconservative. Post-transition rates are seen to increase with increasing weight gain or time until a steady-state post-transition rate is achieved. The corrosion of Zircaloy-4 in a water environment is, therefore, now seen to have a transitory regime in addition to the pretransition and steady-state post-transition regimes. The mathematical description of this transitory regime is shown to fit the following: corrosion rate, R = A . ?W + B, which results in a general equation for weight gain during the transitory regime of ?W = (B/A) . (eAt - 1). This formulation provides a more accurate description of long-term Zircaloy-4 corrosion for use in engineering design than assuming post-transition kinetics based on a linear fit to the cyclic regime following the first cycle.
Zirconium in the Nuclear Industry
Zirconium in the Nuclear Industry
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102705
Category : Science
Languages : en
Pages : 866
Book Description
Publisher: ASTM International
ISBN: 9780803102705
Category : Science
Languages : en
Pages : 866
Book Description
Energy Research Abstracts
Zirconium in the Nuclear Industry
Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
Book Description
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
Book Description
Scientific and Technical Aerospace Reports
Zirconium in the Nuclear Industry
Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Zirconium in the Nuclear Industry
Author: Craig M. Eucken
Publisher: ASTM International
ISBN: 080311463X
Category : Nuclear fuel claddings
Languages : en
Pages : 794
Book Description
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Publisher: ASTM International
ISBN: 080311463X
Category : Nuclear fuel claddings
Languages : en
Pages : 794
Book Description
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
ASTM Special Technical Publication
Modelling Aqueous Corrosion
Author: Kenneth R. Threthewey
Publisher: Springer Science & Business Media
ISBN: 9401111766
Category : Science
Languages : en
Pages : 467
Book Description
All significant studies agree that aqueous corrosion continues to cost nations dearly in almost every area of technological endeavour. Over the past ten years, microcomputers have facilitated an explosion in the power of modelling as a technique in science and engineering. In corrosion they have enabled better understanding of polarization curves, they have transformed the scope of electrochemical impedance measurements and they have placed a large range of electrochemistry at the fingertips of the corrosion scientist. This book focuses on the models, rather than the computing, which have been made possible during the past decade. Aimed at all those with an interest in corrosion and its control, the book draws together the range of new modelling strands, suggests new avenues of approach and generates further momentum for improvements to corrosion management, whether by increased understanding of atomistic processes or by control of large plant.
Publisher: Springer Science & Business Media
ISBN: 9401111766
Category : Science
Languages : en
Pages : 467
Book Description
All significant studies agree that aqueous corrosion continues to cost nations dearly in almost every area of technological endeavour. Over the past ten years, microcomputers have facilitated an explosion in the power of modelling as a technique in science and engineering. In corrosion they have enabled better understanding of polarization curves, they have transformed the scope of electrochemical impedance measurements and they have placed a large range of electrochemistry at the fingertips of the corrosion scientist. This book focuses on the models, rather than the computing, which have been made possible during the past decade. Aimed at all those with an interest in corrosion and its control, the book draws together the range of new modelling strands, suggests new avenues of approach and generates further momentum for improvements to corrosion management, whether by increased understanding of atomistic processes or by control of large plant.