Author: Daniel Charquet
Publisher:
ISBN: 9780803170186
Category : Alloys
Languages : en
Pages : 14
Book Description
In order to optimize zirconium-based alloys, it is usually necessary to understand the relationships and interaction between four different types of parameters: chemical composition, manufacturing process, metallurgical characteristics, and functional properties Examples for various materials show that corrosion resistance depends on the texture and density, distribution, and composition of the precipitate particles. The precipitate composition is determined not only by the alloy chemistry, but also by other factors, such as the cooling rate from the beta phase range. It is also pointed out that some parameters can have opposite effets on nodular and uniform corrosion. Finally, the effects of some impurity elements are described, especially the effect of sulfur on creep and of chlorine on microstructure. The original paper was published by ASTM International in STP 1354, Zirconium in the Nuclear Industry: Twelfth International Symposium, 2000, pp. 314.
Microstructure and Properties of Zirconium Alloys in the Absence of Irradiation
Author: Daniel Charquet
Publisher:
ISBN: 9780803170186
Category : Alloys
Languages : en
Pages : 14
Book Description
In order to optimize zirconium-based alloys, it is usually necessary to understand the relationships and interaction between four different types of parameters: chemical composition, manufacturing process, metallurgical characteristics, and functional properties Examples for various materials show that corrosion resistance depends on the texture and density, distribution, and composition of the precipitate particles. The precipitate composition is determined not only by the alloy chemistry, but also by other factors, such as the cooling rate from the beta phase range. It is also pointed out that some parameters can have opposite effets on nodular and uniform corrosion. Finally, the effects of some impurity elements are described, especially the effect of sulfur on creep and of chlorine on microstructure. The original paper was published by ASTM International in STP 1354, Zirconium in the Nuclear Industry: Twelfth International Symposium, 2000, pp. 314.
Publisher:
ISBN: 9780803170186
Category : Alloys
Languages : en
Pages : 14
Book Description
In order to optimize zirconium-based alloys, it is usually necessary to understand the relationships and interaction between four different types of parameters: chemical composition, manufacturing process, metallurgical characteristics, and functional properties Examples for various materials show that corrosion resistance depends on the texture and density, distribution, and composition of the precipitate particles. The precipitate composition is determined not only by the alloy chemistry, but also by other factors, such as the cooling rate from the beta phase range. It is also pointed out that some parameters can have opposite effets on nodular and uniform corrosion. Finally, the effects of some impurity elements are described, especially the effect of sulfur on creep and of chlorine on microstructure. The original paper was published by ASTM International in STP 1354, Zirconium in the Nuclear Industry: Twelfth International Symposium, 2000, pp. 314.
Microstructure and Properties of Zirconium Alloys in the Absence of Irradiation
Author: D. Charquet
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 12
Book Description
In order to optimize zirconium-based alloys, it is usually necessary to understand the relationships and interactions between four different types of parameters: chemical composition, manufacturing process, metallurgical characteristics, and functional properties. Examples for various materials show that corrosion resistance depends on the texture and density, distribution, and composition of the precipitate particles. The precipitate composition is determined not only by the alloy chemistry, but also by other factors, such as the cooling rate from the beta phase range. It is also pointed out that some parameters can have opposite effects on nodular and uniform corrosion. Finally, the effects of some impurity elements are described, especially the effect of sulfur on creep and of chlorine on microstructure.
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 12
Book Description
In order to optimize zirconium-based alloys, it is usually necessary to understand the relationships and interactions between four different types of parameters: chemical composition, manufacturing process, metallurgical characteristics, and functional properties. Examples for various materials show that corrosion resistance depends on the texture and density, distribution, and composition of the precipitate particles. The precipitate composition is determined not only by the alloy chemistry, but also by other factors, such as the cooling rate from the beta phase range. It is also pointed out that some parameters can have opposite effects on nodular and uniform corrosion. Finally, the effects of some impurity elements are described, especially the effect of sulfur on creep and of chlorine on microstructure.
Mechanical Properties of Irradiated Zirconium, Zircaloy, and Aluminum
Author: Richard E. Schreiber
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 112
Book Description
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 112
Book Description
Zirconium in the Nuclear Industry
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953
Book Description
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953
Book Description
Zirconium in Nuclear Applications
Author: J. H. Schemel
Publisher: ASTM International
ISBN: 9780803107571
Category : Science
Languages : en
Pages : 544
Book Description
Publisher: ASTM International
ISBN: 9780803107571
Category : Science
Languages : en
Pages : 544
Book Description
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.
Evolution of microstructure in zirconium alloys during irradiation
Author: M. Griffiths
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Zirconium in the Nuclear Industry
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
Book Description
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
Book Description
Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth
Author: AV. Tselischev
Publisher:
ISBN:
Category : Composition
Languages : en
Pages : 22
Book Description
The studies of the dislocation structure, phase, and microchemical compositions of alloy Zr-1Nb-1.2Sn-0.35Fe (E635) and its modifications containing Fe from 0.15 to 0.65% were carried out before and after research reactor irradiation at ~350°C to maximal fluence of ~1027 m-2 (E > 0.1 MeV) and at ~60°C. The size and concentration of the a-type loops depend on the alloy composition and fluence and saturate even at low doses (1 dpa). The evolution of the c-component dislocation structure in recrystallized alloys of E365 type is determined by the chemical and phase compositions of alloys specifically, by the Fe/Nb ratio and the threshold dose, and is consistent with the irradiation growth strain acceleration. In E635 alloy containing 0.15%Fe the accelerated growth is observed after the dose of 15 dpa and is attended with the evolution of the c dislocation structure which is similar to Zr-1Nb (E110) alloy behavior. The irradiation induced growth of E635 type alloy containing 0.65% Fe is similar to that of E635 having the normal composition; no
Publisher:
ISBN:
Category : Composition
Languages : en
Pages : 22
Book Description
The studies of the dislocation structure, phase, and microchemical compositions of alloy Zr-1Nb-1.2Sn-0.35Fe (E635) and its modifications containing Fe from 0.15 to 0.65% were carried out before and after research reactor irradiation at ~350°C to maximal fluence of ~1027 m-2 (E > 0.1 MeV) and at ~60°C. The size and concentration of the a-type loops depend on the alloy composition and fluence and saturate even at low doses (1 dpa). The evolution of the c-component dislocation structure in recrystallized alloys of E365 type is determined by the chemical and phase compositions of alloys specifically, by the Fe/Nb ratio and the threshold dose, and is consistent with the irradiation growth strain acceleration. In E635 alloy containing 0.15%Fe the accelerated growth is observed after the dose of 15 dpa and is attended with the evolution of the c dislocation structure which is similar to Zr-1Nb (E110) alloy behavior. The irradiation induced growth of E635 type alloy containing 0.65% Fe is similar to that of E635 having the normal composition; no
A review of microstructure evolution in zirconium alloys during irradiation
Author: M. Griffiths
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description