Neutron Irradiation and Cold Work Effects on Zircaloy-2 Corrosion and Hydrogen Pickup PDF Download
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Author: W. A. Burns
Publisher:
ISBN:
Category :
Languages : en
Pages : 72
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Book Description
Author: W. A. Burns
Publisher:
ISBN:
Category :
Languages : en
Pages : 72
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Book Description
Author: H. P. Maffei
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 17
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Book Description
Nearly 200 pre-autoclaved and weighed coupons of reactor-grade Zircaloy-2 in the annealed, 10, 20, and 40 per cent cold-worked condition have been exposed to the fast neutron flux of the Engineering Test Reactor (ETR) in nominal 540 F pH 10 water for up to 125 days. Flux intensity varied from 0.17 to 1.04 x 1014 nv (>1 Mev), and integrated neutron exposures ranged from 0.3 to 8.2 x 1020 nvt. Comparisons of weight gain and hydrogen pickup results among irradiated specimens and with unirradiated control coupons were used to broaden the area of present knowledge relative to the combined effects of neutron irradiation and cold work on surface chemical reactions and hydrogen absorption in Zircaloy-2. In general, exposure to the in-core coolant environment of the ETR causes an order-of-magnitude increase in average corrosion rates, similar to the effect of superheated steam at a temperature approximately 200 F above the irradiation temperature. In-reactor weight-gain data exhibit an apparent saturation effect with increasing flux intensity, and measured weight gains have been confirmed by optical measurements of oxide film thickness. Direct visual observations and photography at magnifications up to 40 x of irradiated coupons oxidized to weight gains as high as 150 mg/dm2 showed the surfaces to be smooth, glossy, and dark gray or blue-black in color. Some of the coupons appeared to be streak stained, but there were no indications of blistering, spalling, or light-colored oxide even at sharp edges and corners. No significant or consistent variation of weight gain with cold work has been found for material exposed in- or out-of-reactor. No significant effect of flux intensity or integrated flux on hydrogen sorption was observed.
Author: C. L. Whitmarsh
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 74
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1256
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Author: L. A. Bray
Publisher:
ISBN:
Category : Nitration
Languages : en
Pages : 72
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Book Description
Author: Books on Demand
Publisher: ASTM International
ISBN:
Category : Metals
Languages : en
Pages : 723
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Book Description
Author: Sam Stuart
Publisher: Elsevier
ISBN: 1483153495
Category : Technology & Engineering
Languages : en
Pages : 279
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Book Description
Advances in Materials surveys the developments in materials science and technology. This book examines the limitations imposed by materials on the development of technology. Organized into 34 chapters, this book begins with an overview of the techniques in solving the technical challenge in the field of materials. This text then defines the difficult environments considered in this investigation, which include mechanical stress, erosion, chemical attack, and thermal shock at temperatures above about 1200°C. Other chapters consider the successful development of nuclear thermionic converters, which centers heavily on the development of materials capable of enduring rather difficult working conditions for longer periods of time. This book discusses as well the techniques, such as the planar and epitaxy technique, employed in the production of devices. The final chapter deals with the rate of development in the equipment used in the fabrication of plastics. This book is a valuable resource for polymer scientists, materials scientists, engineers, and metallurgists.
Author:
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ISBN:
Category : Aeronautics
Languages : en
Pages : 892
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Author: P. A. Rottenburg
Publisher: Elsevier
ISBN: 148322323X
Category : Technology & Engineering
Languages : en
Pages : 279
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Book Description
Advances in Materials is a record of the proceedings of the symposium on Advances in Materials, held in Manchester College of Science and Technology, Manchester, England in April 1964. The papers collected survey the developments in materials science and technology. The limitations imposed by materials on the progress of modern technology and developments to meet the increasingly exacting requirements of industry are examined. The topics discussed include the challenges to materials science in the chemical industry; progress in materials, designs, and fabrication techniques in the power generation industry; the nature of glass; and effects of temperature and environment on the mechanical behavior of metals. Materials scientists and engineers will find the book a god source of information.
Author: Frederic R. Shober
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
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Book Description
The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
