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Dunn, J.T.; Lipsett, J.J.; Notley, M.J.F.; Spinks, N.J.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1986
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1986
AbstractAbstract
[en] The CANDU reactor system has proven itself to be a world leader in terms of station availability and low total unit energy cost. In 1985 four of the top ten reactor units in the world were CANDU reactors operating in South Korea and Canada. Engineering work is well underway to refine the design of the CANDU 600 and to incorporate state-of-the-art technology, reducing the capital cost and construction schedule for CANDUs of the 1990s. In addition, a smaller CANDU 300 plant has been designed using proven CANDU 600 technology and components, but with an innovative new plant layout that makes it cost competitive with coal-fired plants. For the long term, work on advanced fuel cycles and major system improvements are underway ensuring that CANDU plants will stay competitive well into the next century
Primary Subject
Source
Mar 1986; 33 p; 1990s Water reactor design workshop; Seoul (Republic of Korea); 19 Apr 1986
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Goktepeli, S.
Hacettepe Univ., Fen Bilimleri Enstitusu, Ankara (Turkey)1996
Hacettepe Univ., Fen Bilimleri Enstitusu, Ankara (Turkey)1996
AbstractAbstract
[en] In this study, means of thorium utilization in a CANDU reactor are considered. A once through thorium-DUPIC cycle is analyzed in detail. CANDU has the best neutron economy among the commercially available power reactors, which makes it suitable for many different fuel cycle options. A review of the available fuel cycles is also done in the scope of this study to select an economically viable cycle which does not impose profound changes in the neutronic properties of the core that require remodeling of core and related systems. To create a good model ot the CANDU core for the necessary calculations, the steady state properties of CANDU reactor are analyzed. It is assumed that approximation ot refueling as moving the bundles at a constant velocity is valid. This approximation leads to a corollary; The average cross sections of two adjacent bidirectionally refueled channels are independent of axial location. This is also veritied. A result of this corollary the CANDU core can be modeled only in radial direction in cylindirical geometry. The steady state CANDU core model is prepared using the actual power values and these values are sought in the results. The control systems which effect the neutron flux shape are introduced into the model later in the form of additional absorption cross section and lower diffusion coefficient. The results are in good agreement with the actual values. Several different thorium-DUPIC fuel bundle configurations are considered and the one with 12 Th02 elements in the third ring is found to have similar burnup dependent cross-sections and location infinite multiplication factors. Using the model created, the bundle is tested also in the tull core model and it is tound that this bundle configuration complies with the current refueling scheme. That is, no changes are necessary in the refuelind rate or the control systems. A higher conversion ratio of 0.82 is attained, while the excess reactivity of the core is found to decrease by 0.01 Ak/k. This amount can be easily compensated by the control systems
Original Title
Candu reaktorlerde toryum kullanimi
Primary Subject
Source
1996; 128 p; ISBN 975-491-046-4;
; Available from Hacettepe Univ., Fen Bilimleri Enstitusu, Ankara (TR); Thesis (Ms)

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Miscellaneous
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Thesis/Dissertation
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Kakaria, B. K.
International Nuclear Technology Forum: Future prospects of nuclear power plants and Turkey1994
International Nuclear Technology Forum: Future prospects of nuclear power plants and Turkey1994
AbstractAbstract
No abstract available
Primary Subject
Source
TMMOB Chamber of Mechanical Engineers, Ankara (Turkey); 302 p; ISBN 975-395-117-5;
; 1994; p. 282-285; International Nuclear Technology Forum: Future prospects of nuclear power plants and Turkey; Uluslararasi Nukleer Teknoloji Kurultayi: Nukleer guc santrallarinin gelecegi ve Turkiye; Ankara (Turkey); 12-15 Oct 1993

Record Type
Miscellaneous
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Nash, K.E.; Gavin, M.E.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 21983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 21983
AbstractAbstract
[en] A major step in the development of a large-scale transportation system for irradiated CANDU fuel is being made by Ontario Hydro in the design and construction of a demonstration cask by 1988/89. The system being designed is based on dry transportation with the eventual fully developed system providing for dry fuel loading and unloading. Research carried out to date has demonstrated that it is possible to transport irradiated CANDU fuel in a operationally efficient and simple manner without any damage which would prejudice subsequent automated fuel handling
Primary Subject
Secondary Subject
Source
Oak Ridge National Lab., TN (USA); p. 1017-1023; Dec 1983; p. 1017-1023; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A99/MF A01; 1 as TI84006240
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Report
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Milgram, M.S.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1984
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1984
AbstractAbstract
[en] The characteristics of various advanced fuel cycles possible in CANDU reactors are compared
Primary Subject
Source
Jan 1984; 20 p; Also published in Energy Newsletter vol. 4(3) Oct 1983.
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Report
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Slater, J.B.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1986
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1986
AbstractAbstract
[en] This report is based on informal lectures and presentations made on CANDU Advanced Fuel Cycles over the past year or so, and discusses the future role of CANDU in the changing environment for the Canadian and international nuclear power industry. The changing perspectives of the past decade lead to the conclusion that a significant future market for a CANDU advanced thermal reactor will exist for many decades. Such a reactor could operate in a stand-alone strategy or integrate with a mixed CANDU-LWR or CANDU-FBR strategy. The consistent design focus of CANDU on enhanced efficiency of resource utilization combined with a simple technology to achieve economic targets, will provide sufficient flexibility to maintain CANDU as a viable power producer for both the medium- and long-term future
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Mar 1986; 22 p
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Report
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AbstractAbstract
[en] The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station
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Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 65-70; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
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Miscellaneous
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AbstractAbstract
[en] The CANDU (CANada Deuterium Uranium) design had its begin-ings in the early 1950's with the preliminary engineering studies that led to the 20 MW(e) NPD (Nuclear Power Demonstration) and the 200 MW(e) Douglas Point station . The next decade saw the first operation of both these stations and the commitment of the 2000 MW(e) Pickering and 3000 MW(e) Bruce plants. The present decade has witnessed the excellent performance of Pickering and Bruce and commitments to construct Gentilly-2, Cordoba, Pt. Lepreau, Wolsung, Pickering B, Bruce B and Darlington. In most cases, successive CANDU designs have meant an increase in plant output. Evolutionary developments have been made to fit the requirements of higher ratings and sizes, new regulations, better reliability and maintainability and lower costs. These changes, which are described system by system, have been introduced in the course of engineering parallel reactor projects with overlapping construction schedules -circumstances which ensure close contact with the practical realities of economics, manufacturing functions, construction activities and performance in commissioning. Features for one project furnished alternative concepts for others still on the drawing board and the experience gained in the first application yielded a sound basis for its re-use in succeeding projects. Thus the experiences gained in NPD, Douglas Point, Gentilly-1 and KANUPP have contributed to Pickering and Bruce, which in turn have contributed to the design of Gentilly-2. (author)
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Aug 1978; 18 p; Canadian Nuclear Association 18. annual conference; Ottawa, Ontario, Canada; 11 - 14 Jun 1978
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Report
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Kenchington, J.M.; Ellis, P.J.; Meranda, D.G.
Proceedings of the Canadian Nuclear Society 8. annual conference1987
Proceedings of the Canadian Nuclear Society 8. annual conference1987
AbstractAbstract
[en] The development of leak detection monitoring by the Annulus Gas System (AGS) for the Ontario Hydro Nuclear Stations over the last several years is reviewed. Verified models were used to modify the AGS and provide the operators with safe operating limits. The current AGS design gives the operator an adequate warning to take timely action and if needed to shutdown the reactor safely in a controlled fashion
Primary Subject
Source
Canadian Nuclear Society, Toronto, ON (Canada); 483 p; 1987; p. 425-432; Canadian Nuclear Society 8. annual conference; Saint John, NB (Canada); 16-17 Jun 1987
Record Type
Miscellaneous
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Conference
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Sowagi, J., E-mail: john.sowagi@candu.org
Nuclear Knowledge Management Challenges and Approaches. Summary of an International Conference. Companion CD-ROM2018
Nuclear Knowledge Management Challenges and Approaches. Summary of an International Conference. Companion CD-ROM2018
AbstractAbstract
[en] Leadership development is key to business success. Organizations that invest in leadership development programmes realize improved business results and respond rapidly to changing conditions. This session will examine how the CANDU Owners Group members have engaged in Leadership training development programmes and what impact it has made on the individual, the team and the organization. The focus of these programmes are to build lasting organizational changes through individual growth, effective communication, motivational coaching and team building. Development programmes realize improved business results and respond rapidly to changing conditions. This session will examine how the CANDU Owners Group members have engaged in Leadership training development programmes and what impact it has made on the individual, the team and the organization. The focus of these programmes are to build lasting organizational changes through individual growth, effective communication, motivational coaching and team building. (author)
Primary Subject
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Source
International Atomic Energy Agency, Nuclear Knowledge Management Section, Vienna (Austria); OECD/Nuclear Energy Agency (NEA), Boulogne-Billancourt (France); [1 CD-ROM]; ISBN 978-92-0-108818-5;
; Dec 2018; p. 521; 3. International Conference on Nuclear Knowledge Management Challenges and Approaches; Vienna (Austria); 7-11 Nov 2016; ISSN 0074-1884;
; Also available on-line: https://www-pub.iaea.org/books/IAEABooks/Supplementary_Materials/files/13453/100000/Nuclear-Knowledge-Management-Challenges-Approaches and on 1 CD-ROM attached to the printed STI/PUB/1838 from IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; Abstract only


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