Author: VN. Shishov
Publisher:
ISBN:
Category : Damage dose
Languages : en
Pages : 14
Book Description
The irradiation-induced damage of zirconium alloys subjected to neutron irradiation up to dose levels of ~50 dpa was investigated. Specimens of unalloyed zirconium, Zr-1%Nb, Zr-2.5%Nb and Zr-1%Nb-1.3%Sn-0.4%Fe were irradiated in the BOR-60 reactor over the temperature range 320-420°C. The dose dependence of the irradiation growth strain increased sharply in zirconium and Zr-Nb irradiated at ~350°C at doses above ~10 dpa. In the case of Zr-1%Nb-1.3%Sn-0.4%Fe, it increased at doses of ~37 dpa. Upon increasing the irradiation temperature to 420°C, a sharp accelerated irradiation growth of the Zr-1%Nb alloy began shifting up to about 30 dpa. For the Zr- 1%Nb-1.3%Sn-0.4%Fe, no change of the irradiation growth rate was observed up to a dose of 55 dpa. The onset of increased irradiation growth in alloys correlates with the occurrence of c-component dislocation loops which coincides with a loss of coherence of finely-dispersed precipitates. Post-irradiation annealing experiments demonstrated that a delay in loop formation leads to displacement of the "break-away" beginning in the dose dependence of the irradiation growth in the direction of high doses. The a+c-type dislocation loops were also formed in Zr-1%Nb alloy at high doses, but their influence on the change of macroscopic properties was not observed.
Peculiarities of Structural and Behavioral Changes of Some Zirconium Alloys at Damage Doses of Up to 50 Dpa
Effects of Radiation on Materials
Author: Martin L. Grossbeck
Publisher: ASTM International
ISBN: 0803134770
Category : Materials
Languages : en
Pages : 767
Book Description
Publisher: ASTM International
ISBN: 0803134770
Category : Materials
Languages : en
Pages : 767
Book Description
Oxidation and the Testing of Turbine Oils
Author: Cyril A. Migdal
Publisher: ASTM International
ISBN: 0803134932
Category : Antioxidants
Languages : en
Pages : 929
Book Description
This work presents papers from a December 2005 symposium held in Norfolk, Virginia, and sponsored by ASTM Committee D2 on Petroleum Products and Lubricants and its Subcommittees D02.09 on Oxidation and D02.C0 on Turbine Oils. Contributors include equipment manufacturers, end users, lubricant producers, lubricant additive suppliers, test equipment manufacturers, and standard test method developers. They share information on industry trends, evolving technologies, and changing equipment designs and operating conditions, with a focus on how these factors impact oxidation. Some topics covered include turbine oil performance limits, a new form of the rotating pressure vessel oxidation test, and degradation mechanisms leading to sludge and varnish in modern turbine oil formulations. B&w photos are included. There is no subject index. Migdal is affiliated with Chemtura Corporation.
Publisher: ASTM International
ISBN: 0803134932
Category : Antioxidants
Languages : en
Pages : 929
Book Description
This work presents papers from a December 2005 symposium held in Norfolk, Virginia, and sponsored by ASTM Committee D2 on Petroleum Products and Lubricants and its Subcommittees D02.09 on Oxidation and D02.C0 on Turbine Oils. Contributors include equipment manufacturers, end users, lubricant producers, lubricant additive suppliers, test equipment manufacturers, and standard test method developers. They share information on industry trends, evolving technologies, and changing equipment designs and operating conditions, with a focus on how these factors impact oxidation. Some topics covered include turbine oil performance limits, a new form of the rotating pressure vessel oxidation test, and degradation mechanisms leading to sludge and varnish in modern turbine oil formulations. B&w photos are included. There is no subject index. Migdal is affiliated with Chemtura Corporation.
Creep of Zirconium Alloys in Nuclear Reactors
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
Book Description
Corrosion of Zirconium Alloys in 900 and 1000° Steam
Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 28
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1146
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1146
Book Description
Applications-Related Phenomena in Zirconium and Its Alloys
Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
Book Description
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
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 Preliminary Study of the Aging Behavior of Wrought Columbium-1% Zirconium Alloys
Author: David O. Hobson
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 34
Book Description
Metals Abstracts
Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 712
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 712
Book Description