Post-irradiation examination of power-ramped bruce ngs-a unit 3 fuel exhibiting circumferential end-cap weld failures following a prolonged irradiation at low power

Post-irradiation examination of power-ramped bruce ngs-a unit 3 fuel exhibiting circumferential end-cap weld failures following a prolonged irradiation at low power PDF Author: M. R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Post-irradiation examination of fuel elements from bundles j24518c, j24546c and j24533c discharged from bruce ngs-a unit 1 channel p13 at burnups of 348-774 mw.h/kgu

Post-irradiation examination of fuel elements from bundles j24518c, j24546c and j24533c discharged from bruce ngs-a unit 1 channel p13 at burnups of 348-774 mw.h/kgu PDF Author: M. R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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The continued low power irradiation in the x-2 loop of a defected bruce size fuel element containing an end cap porosity defect and several small cracked hydride blisters

The continued low power irradiation in the x-2 loop of a defected bruce size fuel element containing an end cap porosity defect and several small cracked hydride blisters PDF Author: J. J. Judah
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5

Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201043191
Category : Business & Economics
Languages : en
Pages : 65

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Book Description
This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.

Improvement of Computer Codes Used for Fuel Behaviour Simulation (Fumex-III)

Improvement of Computer Codes Used for Fuel Behaviour Simulation (Fumex-III) PDF Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc
ISBN: 9789201386106
Category : Science
Languages : en
Pages : 0

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Book Description
The modelling of the performance of nuclear fuel is crucial to the operation of nuclear power plants and comprises a key component of the demonstration of nuclear safety. As the demands on fuel performance increase, fuel modelling codes need to develop and cover a wider range of operational and transient conditions. This publication compares the predictions of current fuel modelling codes with data representing a wide range of fuel operational conditions. The results demonstrate both excellent performance and areas for further development of the codes to support advanced fuel operations.

Carbon Nanotubes

Carbon Nanotubes PDF Author: M. Meyyappan
Publisher: CRC Press
ISBN: 0203494938
Category : Science
Languages : en
Pages : 306

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Book Description
Carbon nanotubes, with their extraordinary mechanical and unique electronic properties, have garnered much attention in the past five years. With a broad range of potential applications including nanoelectronics, composites, chemical sensors, biosensors, microscopy, nanoelectromechanical systems, and many more, the scientific community is more moti

Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program

Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program PDF Author: K. M. Wasywich
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159

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Implications of Rising Carbon Dioxide Content of the Atmosphere

Implications of Rising Carbon Dioxide Content of the Atmosphere PDF Author: Conservation Foundation
Publisher:
ISBN:
Category : Air
Languages : en
Pages : 28

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Manufacturing Processes for Design Professionals

Manufacturing Processes for Design Professionals PDF Author: Rob Thompson
Publisher: Thames & Hudson
ISBN: 0500776334
Category : Design
Languages : en
Pages : 528

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Book Description
An encyclopaedic guide to production techniques and materials for product and industrial designers, engineers, and architects. Today's product designers are presented with a myriad of choices when creating their work and preparing it for manufacture. They have to be knowledgeable about a vast repertoire of processes, ranging from what used to be known as traditional "crafts" to the latest technology, to enable their designs to be manufactured effectively and efficiently. Information on the internet about such processes is often unreliable, and search engines do not usefully organize material for designers. This fundamental new resource explores innovative production techniques and materials that are having an impact on the design industry worldwide. Organized into four easily referenced parts—Forming, Cutting, Joining, and Finishing—over seventy manufacturing processes are explained in depth with full technical descriptions; analyses of the typical applications, design opportunities, and considerations each process offers; and information on cost, speed, and environmental impact. The accompanying step-by-step case studies look at a product or component being manufactured at a leading international supplier. A directory of more than fifty materials includes a detailed technical profile, images of typical applications and finishes, and an overview of each material's design characteristics. With some 1,200 color photographs and technical illustrations, specially commissioned for this book, this is the definitive reference for product designers, 3D designers, engineers, and architects who need a convenient, highly accessible, and practical reference.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891

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Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.