Current Topics in the Design and Analysis of Pressure Vessels and Piping, 1997 PDF Download
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Author: Dennis K. Williams
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 272
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Book Description
Contains 30 papers presented in five sessions of the July 1997 conference: numerical analysis of heat exchanger & high temperature components; design with composite metals; non-linear FEA applications; finite element analysis applications; and analysis of bolted joints. Topics include the results of
Author: Dennis K. Williams
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 272
Get Book Here
Book Description
Contains 30 papers presented in five sessions of the July 1997 conference: numerical analysis of heat exchanger & high temperature components; design with composite metals; non-linear FEA applications; finite element analysis applications; and analysis of bolted joints. Topics include the results of
Author: American Society for Metals. Canadian Council
Publisher: Metals Park, Ohio : American Society for Metals
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 288
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Book Description
Author: Canadian Nuclear Society. Conference
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 404
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Book Description
Author: Benjamin Lustman
Publisher:
ISBN: 9781258715175
Category :
Languages : en
Pages : 794
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Book Description
Contributing Authors Include H. Etherington, R. C. Dalzell, D. W. Lillie And Others.
Author: Andrew H. Wilson
Publisher:
ISBN: 9780968091500
Category : Engineering
Languages : en
Pages : 450
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1116
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Book Description
Author: David A. Woodford
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 648
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Book Description
Author: Ian Crossland
Publisher: Elsevier
ISBN: 0857096389
Category : Business & Economics
Languages : en
Pages : 649
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Book Description
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:
Publisher:
ISBN:
Category : Materials
Languages : en
Pages : 412
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Book Description
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201144133
Category : Science
Languages : en
Pages : 311
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Book Description
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.
