Author: DJ. Alexander
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 18
Book Description
The aluminum alloy 6061-T651 was a candidate material for several critical components of the proposed Advanced Neutron Source (ANS) research reactor. In order to determine the effects of irradiation on the mechanical properties of this alloy, irradiations have been conducted in the High Flux Isotope Reactor under conditions that are similar to those predicted for the ANS. Compact and tensile specimens of 6061-T651 aluminum were irradiated at a nominal temperature of 95°C to a thermal neutron fluence of approximately 8 x 1026 m-2 (
The Effects of Irradiation on the Mechanical Properties of 6061-T651 Aluminum Base Metal and Weldments
Author: DJ. Alexander
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 18
Book Description
The aluminum alloy 6061-T651 was a candidate material for several critical components of the proposed Advanced Neutron Source (ANS) research reactor. In order to determine the effects of irradiation on the mechanical properties of this alloy, irradiations have been conducted in the High Flux Isotope Reactor under conditions that are similar to those predicted for the ANS. Compact and tensile specimens of 6061-T651 aluminum were irradiated at a nominal temperature of 95°C to a thermal neutron fluence of approximately 8 x 1026 m-2 (
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 18
Book Description
The aluminum alloy 6061-T651 was a candidate material for several critical components of the proposed Advanced Neutron Source (ANS) research reactor. In order to determine the effects of irradiation on the mechanical properties of this alloy, irradiations have been conducted in the High Flux Isotope Reactor under conditions that are similar to those predicted for the ANS. Compact and tensile specimens of 6061-T651 aluminum were irradiated at a nominal temperature of 95°C to a thermal neutron fluence of approximately 8 x 1026 m-2 (
Effects of Radiation on Materials
Author: R. K. Nanstad
Publisher: ASTM International
ISBN: 080312614X
Category : Materials
Languages : en
Pages : 1135
Book Description
Publisher: ASTM International
ISBN: 080312614X
Category : Materials
Languages : en
Pages : 1135
Book Description
The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 18
Book Description
Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95°C to a fluence of approximately 1026 m−2 (thermal). Testing was conducted from room temperature to 150°C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95°C was not degraded by irradiation, and decreased only slightly at 150°C.
Publisher:
ISBN:
Category :
Languages : en
Pages : 18
Book Description
Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95°C to a fluence of approximately 1026 m−2 (thermal). Testing was conducted from room temperature to 150°C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95°C was not degraded by irradiation, and decreased only slightly at 150°C.
The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum
Author: DJ. Alexander
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 17
Book Description
Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95°C to a fluence of approximately 1026 m-2 (thermal). Testing was conducted from room temperature to 150°C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95°C was not degraded by irradiation, and decreased only slightly at 150°C.
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 17
Book Description
Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95°C to a fluence of approximately 1026 m-2 (thermal). Testing was conducted from room temperature to 150°C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95°C was not degraded by irradiation, and decreased only slightly at 150°C.
Nuclear Science Abstracts
Scientific and Technical Aerospace Reports
Metals and Ceramics Division Progress Report for Period Ending December 31, 1993
Author: D. F. Craig
Publisher:
ISBN:
Category : Ceramics
Languages : en
Pages : 262
Book Description
Publisher:
ISBN:
Category : Ceramics
Languages : en
Pages : 262
Book Description
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 762
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 762
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Metals Abstracts
Advances in Manufacturing and Industrial Engineering
Author: Ranganath M. Singari
Publisher: Springer Nature
ISBN: 9811585423
Category : Technology & Engineering
Languages : en
Pages : 1180
Book Description
This book presents selected peer reviewed papers from the International Conference on Advanced Production and Industrial Engineering (ICAPIE 2019). It covers a wide range of topics and latest research in mechanical systems engineering, materials engineering, micro-machining, renewable energy, industrial and production engineering, and additive manufacturing. Given the range of topics discussed, this book will be useful for students and researchers primarily working in mechanical and industrial engineering, and energy technologies.
Publisher: Springer Nature
ISBN: 9811585423
Category : Technology & Engineering
Languages : en
Pages : 1180
Book Description
This book presents selected peer reviewed papers from the International Conference on Advanced Production and Industrial Engineering (ICAPIE 2019). It covers a wide range of topics and latest research in mechanical systems engineering, materials engineering, micro-machining, renewable energy, industrial and production engineering, and additive manufacturing. Given the range of topics discussed, this book will be useful for students and researchers primarily working in mechanical and industrial engineering, and energy technologies.