Author: R. J. Klassen
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Microstructural dependence of irradiation Creep of zircaloy-2 at 340 k
Author: R. J. Klassen
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Microstructure dependence of irradiation Creep and growth of zirconium alloys
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Effect of microstructure on irradiation Creep and growth of zircaloy pressure tubes in power reactors
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Creep-- Characterization, Damage, and Life Assessments
Author: David A. Woodford
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 648
Book Description
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 648
Book Description
Effects of Anisotropy and Irradiation on the Creep Behavior of Zircaloy-2
Author: Glenn E. Lucas
Publisher: Dissertations-G
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 394
Book Description
Publisher: Dissertations-G
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 394
Book Description
Dose Dependence of Irradiation Creep of Zircaloy-2
Author: DS. Wood
Publisher:
ISBN:
Category : Creep
Languages : en
Pages : 11
Book Description
Periodic diameter measurements have been carried out on a number of the cold worked Zircaloy-2 pressure tubes in a steam generating heavy water reactor. Sufficient results are now available for statistical treatment, and they can be expressed as a function of the dose. The creep strain can be expressed equally well by two relationships, one involving a linear correlation with the dose and the other, a term of dose to the power of 0.6. After 30 years operation it is predicted that the pressure tube creep strains will be within the range of 1 to 3 percent. Observed differences in creep strain on tubes from different suppliers may be due to texture differences.
Publisher:
ISBN:
Category : Creep
Languages : en
Pages : 11
Book Description
Periodic diameter measurements have been carried out on a number of the cold worked Zircaloy-2 pressure tubes in a steam generating heavy water reactor. Sufficient results are now available for statistical treatment, and they can be expressed as a function of the dose. The creep strain can be expressed equally well by two relationships, one involving a linear correlation with the dose and the other, a term of dose to the power of 0.6. After 30 years operation it is predicted that the pressure tube creep strains will be within the range of 1 to 3 percent. Observed differences in creep strain on tubes from different suppliers may be due to texture differences.
Final report on the microstructural evaluation of zircaloy core materials and prediction of irradiation Creep and growth behaviour
Author: M. Griffiths
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Final report on the assessment of irradiation Creep and growth equations and definition of a microstructural assessment program for annealed zircaloy-4
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Irradiation Damage
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 18
Book Description
As indicated in Chapter 1, one of the variables of importance in describing the irradiation creep of zirconium alloys is the degree of exposure of the material to irradiation, often described in terms of neutron fluence. The primary reason for this neutron fluence dependence is that during irradiation an irradiation-induced microstructure evolves, and this microstructure in turn dramatically affects mechanical properties. This microstructure, and hence these property changes, are not entirely fluence dependent, but are functions of the irradiation temperature, the stress state, the neutron energy spectrum, and the initial metallurgical conditions. Consequently, a discussion of irradiation creep in zirconium and the Zircaloys must be prefaced by some review of the nature of the irradiation microstructure, its observed dependence on material and operating conditions, and its effect on deformation behavior.
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 18
Book Description
As indicated in Chapter 1, one of the variables of importance in describing the irradiation creep of zirconium alloys is the degree of exposure of the material to irradiation, often described in terms of neutron fluence. The primary reason for this neutron fluence dependence is that during irradiation an irradiation-induced microstructure evolves, and this microstructure in turn dramatically affects mechanical properties. This microstructure, and hence these property changes, are not entirely fluence dependent, but are functions of the irradiation temperature, the stress state, the neutron energy spectrum, and the initial metallurgical conditions. Consequently, a discussion of irradiation creep in zirconium and the Zircaloys must be prefaced by some review of the nature of the irradiation microstructure, its observed dependence on material and operating conditions, and its effect on deformation behavior.
Metals Abstracts
Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1796
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1796
Book Description