A study of fuel channel and reactor core thermal behaviour during a postulated loec accident

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Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)

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Book Synopsis A study of fuel channel and reactor core thermal behaviour during a postulated loec accident by : D. G. Vandenberghe

Download or read book A study of fuel channel and reactor core thermal behaviour during a postulated loec accident written by D. G. Vandenberghe and published by . This book was released on 1978 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

A study of the effects of principal parameters used in chan ii on the predicted thermal behavior in a fuel channel in loss-of-coolant accident

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)

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Book Synopsis A study of the effects of principal parameters used in chan ii on the predicted thermal behavior in a fuel channel in loss-of-coolant accident by : G. E. Gillespie

Download or read book A study of the effects of principal parameters used in chan ii on the predicted thermal behavior in a fuel channel in loss-of-coolant accident written by G. E. Gillespie and published by . This book was released on 1981 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Heat and Mass Transfer in Severe Nuclear Reactor Accidents

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Publisher : Begell House Publishers
ISBN 13 : 9781567000597
Total Pages : 708 pages
Book Rating : 4.0/5 (5 download)

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Book Synopsis Heat and Mass Transfer in Severe Nuclear Reactor Accidents by : J. T. Rogers

Download or read book Heat and Mass Transfer in Severe Nuclear Reactor Accidents written by J. T. Rogers and published by Begell House Publishers. This book was released on 1996-01-01 with total page 708 pages. Available in PDF, EPUB and Kindle. Book excerpt: Papers and lectures from an international seminar on various heat and mass transfer aspects involved in severe accidents in nuclear power reactors.

Canada Enters the Nuclear Age

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Publisher : McGill-Queen's Press - MQUP
ISBN 13 : 0773566538
Total Pages : 449 pages
Book Rating : 4.7/5 (735 download)

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Book Synopsis Canada Enters the Nuclear Age by : D.G. Hurst

Download or read book Canada Enters the Nuclear Age written by D.G. Hurst and published by McGill-Queen's Press - MQUP. This book was released on 1997-04-19 with total page 449 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written by sixteen of Canada's pioneering nuclear scientists, the book focuses on Canada's nuclear program at AECL's laboratories at Chalk River, Ontario, and Whiteshell, Manitoba, between the years 1943 and 1985. Topics include the organization and operations of AECL's laboratories, nuclear safety and radiation protection, radioisotopes, basic research, development of the CANDU reactor, and the management of radioactive wastes. As well as providing a valuable historical perspective on Canadian science, Canada Enters the Nuclear Age offers useful guidance for innovative scientific development in the future, a future that will depend on developing and nurturing technically sophisticated industry.

Study on Severe Accident Fuel Dispersion Behavior in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory

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Publisher :
ISBN 13 :
Total Pages : 18 pages
Book Rating : 4.:/5 (683 download)

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Book Synopsis Study on Severe Accident Fuel Dispersion Behavior in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory by :

Download or read book Study on Severe Accident Fuel Dispersion Behavior in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory written by and published by . This book was released on 1995 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Core flow blockage events have been identified as a leading contributor to core damage initiation risk in the Advanced Neutron Source (ANS) reactor. During such an accident, insufficient cooling of the fuel in a few adjacent blocked coolant channels out of several hundred channels, could also result in core heatup and melting under full coolant flow condition in other coolant channels. Coolant inertia forces acting on the melt surface would likely break up the melt into small particles. Under thermal-hydraulic conditions of ANS coolant channel, micro-fine melt particles are expected. Heat transfer between melt particle and coolant, which affects the particle breakup characteristics, was studied. The study indicates that the thermal effect on melt fragmentation seems to be negligible because the time corresponding to the breakup due to hydrodynamic forces is much shorter than the time for the melt surface to solidify. The study included modeling and analyses to predict transient behavior and transport of debris particles throughout the coolant system. The transient model accounts for the surface forces acting on the particle that result from the pressure variation on the surface, inertia, virtual mass, viscous force due to the relative motion of the particle in the coolant, gravitation, and resistance due to inhomogeneous coolant velocity radially across piping due to expected turbulent coolant motions. The results indicate that debris particles would reside longest in the heat exchangers because of lower coolant velocity there. Also they are entrained and move together in a cloud.

Preliminary Best Estimate Analysis of Whole Core LOCA Behavior. [PWR].

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Preliminary Best Estimate Analysis of Whole Core LOCA Behavior. [PWR]. by :

Download or read book Preliminary Best Estimate Analysis of Whole Core LOCA Behavior. [PWR]. written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Analyses of fuel behavior during LOCA have generally been performed for a single fuel rod (the ''hot rod'') of a reactor core. This type of analysis, even using best estimate assumptions, does not apply to the behavior of majority of the fuel rods in the core. Furthermore, burnup effects are normally considered only so far as the fill gas pressure and, partly, the stored energy are concerned. However, the gap closure and additional burnup effects strongly influence the fuel behavior during a transient. Consequently, the power history should be simulated for the fuel rod during its life prior to the accident analysis. The paper describes a preliminary best estimate analysis using the FRAP-S and FRAP-T codes, to determine the behavior of the fuel rods in an operating commercial 15 x 15 PWR core during a postulated loss of coolant accident (LOCA). The blowdown, refill, and reflood phases of the core were considered.

Analysis of Loss-of-coolant Accident for a Fast-spectrum Lithium-cooled Nuclear Reactor for Space-power Applications

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Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.F/5 ( download)

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Book Synopsis Analysis of Loss-of-coolant Accident for a Fast-spectrum Lithium-cooled Nuclear Reactor for Space-power Applications by : George E. Turney

Download or read book Analysis of Loss-of-coolant Accident for a Fast-spectrum Lithium-cooled Nuclear Reactor for Space-power Applications written by George E. Turney and published by . This book was released on 1972 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fuel Temperatures in an Argonaut Reactor Core Following a Hypothetical Design Basis Accident (DBA)

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Publisher :
ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Fuel Temperatures in an Argonaut Reactor Core Following a Hypothetical Design Basis Accident (DBA) by : G. Edward Cort

Download or read book Fuel Temperatures in an Argonaut Reactor Core Following a Hypothetical Design Basis Accident (DBA) written by G. Edward Cort and published by . This book was released on 1981 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:

A Comparative Study of Reactor Core Meltdown and the Assessment of Post Accident Heat Removal

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Publisher :
ISBN 13 :
Total Pages : 142 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis A Comparative Study of Reactor Core Meltdown and the Assessment of Post Accident Heat Removal by : Adib Shamaoun

Download or read book A Comparative Study of Reactor Core Meltdown and the Assessment of Post Accident Heat Removal written by Adib Shamaoun and published by . This book was released on 1985 with total page 142 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Thermal Analysis of an Advanced Reactor Core During Loss of Forced Cooling Accident Conditions

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Publisher :
ISBN 13 :
Total Pages : 188 pages
Book Rating : 4.:/5 (125 download)

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Book Synopsis Thermal Analysis of an Advanced Reactor Core During Loss of Forced Cooling Accident Conditions by : Sudipto Ranendra Roy

Download or read book Thermal Analysis of an Advanced Reactor Core During Loss of Forced Cooling Accident Conditions written by Sudipto Ranendra Roy and published by . This book was released on 1984 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Effect of Oxygen on the Failure of Reactor Fuel Sheaths During a Postulated Loss-of-coolant Accident

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Publisher : Pinawa, Man. : Whiteshell Nuclear Research Establishment
ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.:/5 (159 download)

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Book Synopsis The Effect of Oxygen on the Failure of Reactor Fuel Sheaths During a Postulated Loss-of-coolant Accident by : Atomic Energy of Canada Limited

Download or read book The Effect of Oxygen on the Failure of Reactor Fuel Sheaths During a Postulated Loss-of-coolant Accident written by Atomic Energy of Canada Limited and published by Pinawa, Man. : Whiteshell Nuclear Research Establishment. This book was released on 1983 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

An Experimental Investigation of Boiling Water Nuclear Reactor Parallel Channel Effects During a Postulated Loss-of-coolant Accident

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ISBN 13 :
Total Pages : 1354 pages
Book Rating : 4.:/5 (967 download)

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Book Synopsis An Experimental Investigation of Boiling Water Nuclear Reactor Parallel Channel Effects During a Postulated Loss-of-coolant Accident by : W. M. Conlon

Download or read book An Experimental Investigation of Boiling Water Nuclear Reactor Parallel Channel Effects During a Postulated Loss-of-coolant Accident written by W. M. Conlon and published by . This book was released on 1982 with total page 1354 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear fuel behaviour in loss-of-coolant accident (LOCA) conditions

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Publisher :
ISBN 13 : 9789264990913
Total Pages : 373 pages
Book Rating : 4.9/5 (99 download)

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Book Synopsis Nuclear fuel behaviour in loss-of-coolant accident (LOCA) conditions by :

Download or read book Nuclear fuel behaviour in loss-of-coolant accident (LOCA) conditions written by and published by . This book was released on 2009 with total page 373 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Ignalina RBMK-1500 : a source book

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Publisher :
ISBN 13 : 9789986492351
Total Pages : 198 pages
Book Rating : 4.4/5 (923 download)

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Book Synopsis Ignalina RBMK-1500 : a source book by : Kazys Almenas

Download or read book Ignalina RBMK-1500 : a source book written by Kazys Almenas and published by . This book was released on 1998 with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Energy Research Abstracts

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Publisher :
ISBN 13 :
Total Pages : 1194 pages
Book Rating : 4.U/5 (183 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1978 with total page 1194 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Applications of Research Reactors

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Publisher : International Atomic Energy Agency
ISBN 13 : 9789201450104
Total Pages : 108 pages
Book Rating : 4.4/5 (51 download)

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Book Synopsis Applications of Research Reactors by : International Atomic Energy Agency

Download or read book Applications of Research Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2014 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.

Nuclear Regulatory Commission Issuances

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Publisher :
ISBN 13 :
Total Pages : 950 pages
Book Rating : 4.3/5 (129 download)

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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: