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AbstractAbstract
[en] A brief description of the seismic criteria established for use with the Steam Generating Heavy Water Reactor (SCHWR) and taken for the Heysham II Project is given. The qualification strategy adopted for Heysham II is described, and a brief overview is given of some of the more important design changes required for seismic purposes on that station
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GA Technologies, Inc., San Diego, CA (USA); p. 237-274; Jun 1983; p. 237-274; IAEA IWGGCR specialists' meeting on gas-cooled reactor seismic design problems and solutions; San Diego, CA (USA); 30 Aug - 1 Sep 1982; Available from NTIS, PC A13/MF A01; 1 as DE83014928
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Report
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Conference
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
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Source
European nuclear conference; Paris, France; 21 Apr 1975; Published in summary form only.
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Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 20 p. 102-104
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AbstractAbstract
[en] Equipment used in the in-vessel regions of AGRs is exposed to a variety of potential damage mechanisms, high temperature, oxidation, noise and irradiation. Some of this equipment is required to operate reliably, without access for maintenance, over the full 30 years design life of the reactor. An integrated approach to the design, development and manufacture of this equipment has to be adopted to ensure attainment of the design objectives. The paper will describe the design, development and manufacture of some of the more important items of equipment supplied for the Hartlepool and Heysham AGRs, particularly those associated with the fuel handling and reactor safety systems. (author)
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British Nuclear Energy Society, London; p. 377-384; ISBN 0 7277 0083 9; ; 1979; p. 377-384; British Nuclear Energy Society; London; Conference on welding and fabrication in the nuclear industry; London, UK; 3 - 5 Apr 1979
Record Type
Book
Literature Type
Conference
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Elston, J.T.
Nuclear power performance and safety. V.2. Achievements in construction and operation1988
Nuclear power performance and safety. V.2. Achievements in construction and operation1988
AbstractAbstract
[en] The design of the station is based on that employed at Hinkley Point 'B' in Somerset, modified to meet more recent safety criteria and to provide increased operating margins. Strict control was imposed on design changes using the Quality Assurance procedures developed to define the duties and responsibilities of all parties involved in the project. The management organisation is a well-defined hierarchy headed by a Project Manager supported by a headquarters-based project engineering team and a site-based construction management team. Contracts have been awarded to a large number of firms and novel incentives have been developed to encourage timely completion. The National Nuclear Corporation Ltd. is Agent to the CEGB for the design and management of the nuclear island whilst CEGB encompasses overall project direction as well as direct control of balance of plant contracts. Emphasis has been placed on the reduction of site fabrication of large critical components and site employment policies have served to harmonize employment arrangements. The construction of the project has been achieved within the original schedule and within 5% of the original cost estimate. During the commissioning phase, however, an unexpected problem was identified which stemmed from a small change from the Hinkley Point 'B' design made in the conceptual stages, and this caused a delay of several months to the first unit. Fuel loading is due to commence in July 1987 with the prospect of power raising by the end of the year. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Proceedings series; 473 p; ISBN 92-0-050188-5; ; 1988; v. 2 p. 45-51; IAEA; Vienna (Austria); International conference on nuclear power performance and safety; Vienna (Austria); 28 Sep - 2 Oct 1987; IAEA-CN--48/170
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Book
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Conference
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Related RecordRelated Record
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AbstractAbstract
[en] A detailed emergency plan for the reactor is presented. Definitions, conditions for taking action, duties of staff, emergency control centres and equipment, communications, both internal and external, hazard assessment, including iodine inhalation and radioactive deposition procedures, collaboration with other bodies, warnings to the public and exercises are among topics described. (author)
Primary Subject
Source
1985; vp; Central Electricity Generating Board; London (UK)
Record Type
Book
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
White, C.M.
Experience in the design, construction, and operation of prestressed concrete pressure vessels and containments for nuclear reactors1976
Experience in the design, construction, and operation of prestressed concrete pressure vessels and containments for nuclear reactors1976
AbstractAbstract
[en] A brief description is given of the steel liners for the prestressed concrete pressure vessels at Heysham Nuclear Power Station. The factors which determine construction strategy and the extent of shop prefabrication of the liners are then discussed and finally some manufacturing operations which contain an element of novelty are described. (author)
Primary Subject
Source
Institution of Mechanical Engineers, London (UK); p. 381-388; ISBN 0 85298 339 5; ; 1976; Mechanical Engineering Pub. Ltd. for Institution of Mechanical Engineers; London; Conference on experience in the design, construction, and operation of prestressed concrete pressure vessels and containments for Nuclear Reactors; York, UK; 8 - 12 Sep 1975
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Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A comparison of the civil construction works experience on Heysham I nuclear power plant with that of Heysham II following the introduction of a quality system provided on insight into the benefits resulting from quality assurance. These included: improved administration, better identification of responsibility and improved communications, improved pre-planning, better records, and greater control over activities with Suppliers and Sub-contractors. For Heysham II the full benefits of quality assurance were realised by integrating it into the management system and through the practical understanding achieved with the Client. (U.K.)
Primary Subject
Source
British Nuclear Forum, London; 112 p; 1985; p. 46-52; British Nuclear Forum; London (UK); One-day conference on the role of quality assurance in the nuclear industry; London (UK); 30 Oct 1985; Price Pound 34.00
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Book
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Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Hughes, A.N.; Bellwood, G.N.; Paton, A.A.
Experience in the design, construction, and operation of prestressed concrete pressure vessels and containments for nuclear reactors1976
Experience in the design, construction, and operation of prestressed concrete pressure vessels and containments for nuclear reactors1976
AbstractAbstract
[en] The building of the top cap poses problems because of the number of penetrations to be cast therein. The fuel and control system routes need to be tightly specified and controlled so that during station life misalignments do not occur which interfere with the fuelling and control operations. The paper outlines the route requirements and illustrates how these affect the tolerances and movements which can be allowed at various stages of construction. Development work is discussed to show the necessity of resolving the different priorities of design, programme and overall pressure vessel construction requirements, so that the reactor build is not inhibited by the special demands of the top cap, and the integration of the monitoring and survey systems during the top cap build are explained. (author)
Primary Subject
Source
Institution of Mechanical Engineers, London (UK); p. 327-333; ISBN 0 85298 339 5; ; 1976; Mechanical Engineering Pub. Ltd. for Institution of Mechanical Engineers; London; Conference on experience in the design, construction, and operation of prestressed concrete pressure vessels and containments for Nuclear Reactors; York, UK; 8 - 12 Sep 1975
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Grant, J.A.
Welding and fabrication in the nuclear industry. Proceedings of the conference held in London, 3-5 April 19791979
Welding and fabrication in the nuclear industry. Proceedings of the conference held in London, 3-5 April 19791979
AbstractAbstract
[en] In 1968 Babcock and Wilcox (Operations) Ltd., received an order from the CEGB to design, manufacture, install and commission 16 Steam Generators for 2 x 660 Mw (e) Advanced Gas Cooled Reactor Power Station at Hartlepool. This order was followed in 1970 by a similar order for the Heysham Power Station. The design and manufacture of the Steam Generators represented a major advance in technology and the paper discusses the methods by which a manufacturing facility was developed, by the Production Division of Babcock, to produce components to a quality, complexity and accuracy unique in the U.K. commercial boilermaking industry. The discussion includes a brief design background, a description of the Steam Generators and a view of the Production Division background. This is followed by a description of the organisation of the technological development and a consideration of the results. (author)
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British Nuclear Energy Society, London; p. 111-116; ISBN 0 7277 0083 9; ; 1979; p. 111-116; British Nuclear Energy Society; London; Conference on welding and fabrication in the nuclear industry; London, UK; 3 - 5 Apr 1979
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Book
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Conference
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Crosslands, B.; Braithwaite, A.B.M.; Chapman, H.E.
Welding and fabrication in the nuclear industry. Proceedings of the conference held in London, 3-5 April 19791979
Welding and fabrication in the nuclear industry. Proceedings of the conference held in London, 3-5 April 19791979
AbstractAbstract
[en] The paper is concerned with the explosive plugging of the boiler and reheater circuits of the AGR pod boilers for the Hartlepool and Heysham power stations. A point charge system for the boiler circuit plugging and a rim charge system for the larger plugs in the reheater circuit are described. The ligament distortion due to plugging has been overcome by a simple support bung. The paper also describes the design and development of a remote controlled manipulator and the various tool heads, which are required to perform all the various operations in reheater tube plugging. (author)
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Source
British Nuclear Energy Society, London; p. 297-304; ISBN 0 7277 0083 9; ; 1979; p. 297-304; British Nuclear Energy Society; London; Conference on welding and fabrication in the nuclear industry; London, UK; 3 - 5 Apr 1979
Record Type
Book
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Conference
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Reference NumberReference Number
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