Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions

Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions PDF Author: AA. Bauer
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 10

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Book Description
A program is being conducted to determine the mechanical behavior of irradiated Zircaloy-4 fuel rod cladding subjected to anneals under temperature and time conditions that simulate various off-normal and transient reactor operating conditions. This paper reports the initial phase of the program, which is a study of changes in hardness and tensile properties that accompany isothermal and transient anneals. A special transient annealing apparatus was built to subject specimens to the desired temperature/time conditions. Hardness and tensile strength decreased with increase in the maximum annealing temperature from 800°F (425°C) to 1300°F (705°C). Changes above 1100°F (595°C) were related to recrystallization and grain growth.

Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions

Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions PDF Author: AA. Bauer
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 10

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Book Description
A program is being conducted to determine the mechanical behavior of irradiated Zircaloy-4 fuel rod cladding subjected to anneals under temperature and time conditions that simulate various off-normal and transient reactor operating conditions. This paper reports the initial phase of the program, which is a study of changes in hardness and tensile properties that accompany isothermal and transient anneals. A special transient annealing apparatus was built to subject specimens to the desired temperature/time conditions. Hardness and tensile strength decreased with increase in the maximum annealing temperature from 800°F (425°C) to 1300°F (705°C). Changes above 1100°F (595°C) were related to recrystallization and grain growth.

Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions

Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions PDF Author: H. Tsai
Publisher:
ISBN:
Category : Axial specimens
Languages : en
Pages : 16

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Book Description
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircaloy cladding subjected to the mechanical conditions and temperatures associated with reactivity-initiated accidents (RIA) and loss-of-coolant accidents (LOCA). Miniature ring-stretch specimens were designed to induce both uniaxial and plane-strain states of stress in the transverse (hoop) direction of the cladding. Also, longitudinal tube specimens were also designed to determine the constitutive properties in the axial direction. Finite-element analysis (FEA) and experimental parameters and results were closely coupled to optimize an accurate determination of the stress-strain response and to induce fracture behavior representative of accident conditions. To determine the constitutive properties, a procedure was utilized to transform measured values of load and displacement to a stress-strain response under complex loading states. Additionally, methods have been developed to measure true plastic strains in the gauge section and the initiation of failure using real-time data analysis software. Strain rates and heating conditions have been selected based on their relevance to the mechanical response and temperatures of the cladding during the accidents.

Irradiation Effects on the Microstructure and Properties of Metals

Irradiation Effects on the Microstructure and Properties of Metals PDF Author:
Publisher: ASTM International
ISBN:
Category : Metals
Languages : en
Pages : 491

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Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions

Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 16

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Book Description
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircaloy cladding subjected to the mechanical conditions and temperatures associated with reactivity-initiated accidents (RIA) and loss-of-coolant accidents (LOCA). Miniature ring-stretch specimens were designed to induce both uniaxial and plane-strain states of stress in the transverse (hoop) direction of the cladding. Also, longitudinal tube specimens were also designed to determine the constitutive properties in the axial direction. Finite-element analysis (FEA) and experimental parameters and results were closely coupled to optimize an accurate determination of the stress-strain response and to induce fracture behavior representative of accident conditions. To determine the constitutive properties, a procedure was utilized to transform measured values of load and displacement to a stress-strain response under complex loading states. Additionally, methods have been developed to measure true plastic strains in the gauge section and the initiation of failure using real-time data analysis software. Strain rates and heating conditions have been selected based on their relevance to the mechanical response and temperatures of the cladding during the accidents.

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5 PDF Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40

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NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 64

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Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5 PDF Author:
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 452

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Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1190

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Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 760

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ASTM Special Technical Publication

ASTM Special Technical Publication PDF Author:
Publisher:
ISBN:
Category : Materials
Languages : en
Pages : 504

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