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Measurement Of End Slopes Of Pressure Tubes In Rolled Joints Removed From Candu Power Reactors
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Book Synopsis Measurement of end slopes of pressure tubes in rolled joints removed from CANDU power reactors by : I. R. Emmerton
Download or read book Measurement of end slopes of pressure tubes in rolled joints removed from CANDU power reactors written by I. R. Emmerton and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Procedure for the measurement of as-rolled resdiual stresses and end slopes of pressure tube rolled joints removed from CANDU reactors by : S. A. Donohue
Download or read book Procedure for the measurement of as-rolled resdiual stresses and end slopes of pressure tube rolled joints removed from CANDU reactors written by S. A. Donohue and published by . This book was released on 1999 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Post-service residual stress measurements of b6-k01 pressure tube-to-end fitting rolled joint by : B. L. Wotton
Download or read book Post-service residual stress measurements of b6-k01 pressure tube-to-end fitting rolled joint written by B. L. Wotton and published by . This book was released on 1998 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Simulations of ultrasonic inspection of engineered components have been performed at chalk river laboratories of aecl for over 10 years. the computer model, called ewe for elastic wave equations, solves those equations using a novel finite difference scheme. it simulates the propagation of an ultrasonic wave from the transducer to a flaw, the scatter of waves from the flaw, and measurement of signals at a receive transducer. regions of different materials, water and steel for example, can be simulated. in addition, regions with slightly different material properties from the parent material can be investigated. the two major types of output are displays of the ultrasonic waves inside the component and the corresponding amplitude or a-scans. the ewe model has been applied to the inspection of large pipes in a nuclear plant, gas pipeline welds and steam generator tubes. most recent work has dealt with the ultrasonic inspection of pressure tubes in candu reactors. pressure tube inspections can reliably detect and size defects; however, there are improvements that can be made. for example, knowing the sharpness of a flaw-tip is crucial for effective fitness-for-service assessments. computer modelling of the ultrasonic inspection of flaws with different root radii has suggested inspection techniques that provide flaw tip radius information. a preliminary investigation of these methods has been made in the laboratory. the basis for the model will be reviewed at the presentation. then the results of computer simulations will be displayed on a pc using an interactive program that analyzes simulated a-scans. this software tool gives operators direct access to the results of computer simulations.
Book Synopsis Fabrication and testing of pressure tube/end fitting rolled joints, using thin-walled hubs for 300 mw reactor fuel channels by : R. C. Schaubel
Download or read book Fabrication and testing of pressure tube/end fitting rolled joints, using thin-walled hubs for 300 mw reactor fuel channels written by R. C. Schaubel and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Zirconium in the Nuclear Industry by : George P. Sabol
Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 1996 with total page 907 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Metals Abstracts written by and published by . This book was released on 1985 with total page 1218 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 by : International Atomic Energy Agency
Download or read book Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 written by International Atomic Energy Agency and published by . This book was released on 2019-12-19 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Zirconium in the Nuclear Industry by : Craig M. Eucken
Download or read book Zirconium in the Nuclear Industry written by Craig M. Eucken and published by ASTM International. This book was released on 1991 with total page 794 pages. Available in PDF, EPUB and Kindle. Book excerpt: The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Book Synopsis Nuclear Regulatory Commission Issuances by : U.S. Nuclear Regulatory Commission
Download or read book Nuclear Regulatory Commission Issuances written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1979 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Passive Nondestructive Assay of Nuclear Materials by : Doug Reilly
Download or read book Passive Nondestructive Assay of Nuclear Materials written by Doug Reilly and published by . This book was released on 1991 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Corrosion Science and Engineering by : Damien Feron
Download or read book Nuclear Corrosion Science and Engineering written by Damien Feron and published by Elsevier. This book was released on 2012-02-21 with total page 1073 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches
Book Synopsis Zirconium in the Nuclear Industry by : Gerry D. Moan
Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Characterisation of Radiation Damage by Transmission Electron Microscopy by : M.L Jenkins
Download or read book Characterisation of Radiation Damage by Transmission Electron Microscopy written by M.L Jenkins and published by CRC Press. This book was released on 2000-11-21 with total page 233 pages. Available in PDF, EPUB and Kindle. Book excerpt: Characterization of Radiation Damage by Transmission Electron Microscopy details the electron microscopy methods used to investigate complex and fine-scale microstructures, such as those produced by fast-particle irradiation of metals or ion implantation of semiconductors. The book focuses on the methods used to characterize small point-defect clus
Book Synopsis Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment by : Jyeshtharaj Joshi
Download or read book Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment written by Jyeshtharaj Joshi and published by Woodhead Publishing. This book was released on 2019-06-15 with total page 888 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization
Book Synopsis Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications by : International Atomic Energy Agency
Download or read book Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications written by International Atomic Energy Agency and published by . This book was released on 2014-02-19 with total page 311 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of an IAEA cooperated research project (CRP) on benchmarking severe accident computer codes for heavy water reactor applications. The CRP scope included the identification and selection of a severe accident sequence, selection of appropriate geometrical and boundary conditions, conduct of benchmark analyses, comparison of the results of all code outputs, evaluation of the capabilities of computer codes to predict important severe accident phenomena, and the proposal of necessary code improvements and/or new experiments to reduce uncertainties. The summary report provides a comparison of key results obtained from five participating countries and concludes with lessons learned and recommendations for the future.
Book Synopsis Nuclear Fuel Cycle Science and Engineering by : Ian Crossland
Download or read book Nuclear Fuel Cycle Science and Engineering written by Ian Crossland and published by Elsevier. This book was released on 2012-09-21 with total page 649 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field. Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management. With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. Provides a comprehensive and holistic review of the complete nuclear fuel cycle Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication
Author :International Atomic Energy Agency Publisher :IAEA Nuclear Energy ISBN 13 :9789201029140 Total Pages :0 pages Book Rating :4.0/5 (291 download)
Book Synopsis Ageing Management of Concrete Structures in Nuclear Power Plants by : International Atomic Energy Agency
Download or read book Ageing Management of Concrete Structures in Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA Nuclear Energy. This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is one in a series of reports on the assessment and management of ageing of major nuclear power plant (NPP) components. Current practices for assessment of safety margins (fitness for service) and inspection, monitoring and mitigation of ageing related degradation of selected concrete structures related to NPPs are documented. Implications for and differences in new reactor designs are discussed. This information is intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues.
