Author: A. W. Stewart
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Zircaloy-4 fuel sheath specimens 15.2 mm diameter by 0.42 mm wall thickness with beryllium-brazed appendages have been laboratory tested at high temperature with internal gas pressurization and inert gas shielding of the outer surfaces. with sufficient hoop stress at temperatures less than 1073 k cracks, which were due to a beryllium assisted crack penetration mechanism, were found to occur at the appendages. formulae to predict the beryllium penetration and rupture have been derived by westinghouse canada ltd. based on data from direct resistance-heated specimens. the formulae are thought to be able to predict the phenomenon in fuel sheaths with changing temperature/pressure histories. a series of tests was done by canadian general electric to determine the formulae ability to predict the occurrence of beryllium assisted crack penetration in specimens heated indirectly with internal heaters. the tests showed: 1) there is an incubation period before any beryllium assisted crack penetration occurs. 2) at sheath temperatures below approximately equal to 1073 k sheath rupture by excessive mechanical strain will preclude rupture by beryllium assisted crack penetration. 3) the formulae predicted rupture times above and below the braze alloy melting temperature within the previously determined confidence limits. 4) predictions of beryllium assisted crack penetration rupture for specimens with changing temperature/pressure histories were of similar accuracy to predictions of isothermal tests. 5) specimens with an appendage plane of one bearing pad and three spacer pads behaved similarly to the specimens with four spacer pads on which the formulae were based.
Fabrication details for five NRU-114 natural b.l.w. fuel bundles of the gentilly design
Author: A. W. Stewart
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Zircaloy-4 fuel sheath specimens 15.2 mm diameter by 0.42 mm wall thickness with beryllium-brazed appendages have been laboratory tested at high temperature with internal gas pressurization and inert gas shielding of the outer surfaces. with sufficient hoop stress at temperatures less than 1073 k cracks, which were due to a beryllium assisted crack penetration mechanism, were found to occur at the appendages. formulae to predict the beryllium penetration and rupture have been derived by westinghouse canada ltd. based on data from direct resistance-heated specimens. the formulae are thought to be able to predict the phenomenon in fuel sheaths with changing temperature/pressure histories. a series of tests was done by canadian general electric to determine the formulae ability to predict the occurrence of beryllium assisted crack penetration in specimens heated indirectly with internal heaters. the tests showed: 1) there is an incubation period before any beryllium assisted crack penetration occurs. 2) at sheath temperatures below approximately equal to 1073 k sheath rupture by excessive mechanical strain will preclude rupture by beryllium assisted crack penetration. 3) the formulae predicted rupture times above and below the braze alloy melting temperature within the previously determined confidence limits. 4) predictions of beryllium assisted crack penetration rupture for specimens with changing temperature/pressure histories were of similar accuracy to predictions of isothermal tests. 5) specimens with an appendage plane of one bearing pad and three spacer pads behaved similarly to the specimens with four spacer pads on which the formulae were based.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Zircaloy-4 fuel sheath specimens 15.2 mm diameter by 0.42 mm wall thickness with beryllium-brazed appendages have been laboratory tested at high temperature with internal gas pressurization and inert gas shielding of the outer surfaces. with sufficient hoop stress at temperatures less than 1073 k cracks, which were due to a beryllium assisted crack penetration mechanism, were found to occur at the appendages. formulae to predict the beryllium penetration and rupture have been derived by westinghouse canada ltd. based on data from direct resistance-heated specimens. the formulae are thought to be able to predict the phenomenon in fuel sheaths with changing temperature/pressure histories. a series of tests was done by canadian general electric to determine the formulae ability to predict the occurrence of beryllium assisted crack penetration in specimens heated indirectly with internal heaters. the tests showed: 1) there is an incubation period before any beryllium assisted crack penetration occurs. 2) at sheath temperatures below approximately equal to 1073 k sheath rupture by excessive mechanical strain will preclude rupture by beryllium assisted crack penetration. 3) the formulae predicted rupture times above and below the braze alloy melting temperature within the previously determined confidence limits. 4) predictions of beryllium assisted crack penetration rupture for specimens with changing temperature/pressure histories were of similar accuracy to predictions of isothermal tests. 5) specimens with an appendage plane of one bearing pad and three spacer pads behaved similarly to the specimens with four spacer pads on which the formulae were based.
Canada Enters the Nuclear Age
Author: Atomic Energy of Canada Limited
Publisher: McGill-Queen's Press - MQUP
ISBN: 9780773516014
Category : Business & Economics
Languages : en
Pages : 466
Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR
Publisher: McGill-Queen's Press - MQUP
ISBN: 9780773516014
Category : Business & Economics
Languages : en
Pages : 466
Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR
A History of the Atomic Energy Control Board
Author: Gordon H. E. Sims
Publisher: Minister of Supply and Services Canada
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
Book Description
Hull, Que. : Supply and Services Canada, 1980, c1981.
Publisher: Minister of Supply and Services Canada
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
Book Description
Hull, Que. : Supply and Services Canada, 1980, c1981.
Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program
Author: K. M. Wasywich
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Reactor Burn-up Physics
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 312
Book Description
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 312
Book Description
Implementation Strategies and Tools for Condition Based Maintenance at Nuclear Power Plants
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN: 9789201039071
Category : Business & Economics
Languages : en
Pages : 178
Book Description
There is a need to optimise the maintenance of nuclear power plants, both to improve reliability and increase competitiveness. The tendency is to move from preventative (time based) maintenance to one dependent on the condition of plant and its components. This publication collects and analyses proven condition based maintenance strategies and techniques in Member States as well as selected papers on maintenance optimisation.
Publisher: IAEA
ISBN: 9789201039071
Category : Business & Economics
Languages : en
Pages : 178
Book Description
There is a need to optimise the maintenance of nuclear power plants, both to improve reliability and increase competitiveness. The tendency is to move from preventative (time based) maintenance to one dependent on the condition of plant and its components. This publication collects and analyses proven condition based maintenance strategies and techniques in Member States as well as selected papers on maintenance optimisation.
PWR steam generator chemical cleaning
Author: United States. Department of Energy. Division of Nuclear Power Development
Publisher:
ISBN:
Category :
Languages : en
Pages : 354
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 354
Book Description
Power Reactor Technology
Nuclear Power
Author: Walter C. Patterson
Publisher: Penguin Group
ISBN:
Category : Science
Languages : en
Pages : 264
Book Description
"To those who feel that nuclear matters should not be left to battling experts, Nuclear Power offers essential support. In lively, everyday language it describes nuclear technology and how it works - and sometimes fails to work - and analyses the issues which face the policy-makers. In this comprehensively revised and up-dated second edition, the author discusses in detail recent nuclear developments world wide."--
Publisher: Penguin Group
ISBN:
Category : Science
Languages : en
Pages : 264
Book Description
"To those who feel that nuclear matters should not be left to battling experts, Nuclear Power offers essential support. In lively, everyday language it describes nuclear technology and how it works - and sometimes fails to work - and analyses the issues which face the policy-makers. In this comprehensively revised and up-dated second edition, the author discusses in detail recent nuclear developments world wide."--
Reactor Development
Author: Lyle B. Borst
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 6
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 6
Book Description