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AbstractAbstract
[en] The decommissioning of nuclear power plants and fuel cycle centers in the United Kingdom has become an emotive subject and has, along with waste management, been blamed for the apparent demise of the nuclear power industry. During the early eighties, in the United Kingdom, it was becoming obvious that some of the older defence facilities could not be left in their existing condition for much longer. A program was drawn up and discussions held with the responsible authorities. At about the same time, consideration was also being given to the dismantling of the nuclear facilities that were or had been used as part of the programme of nuclear fuel cycle services to the civil nuclear programme in United Kingdom. As a consequence of these activities, a comprehensive decommissioning policy and programme for the defence related and fuel cycle centers had been drawn up. In addition to this, the Atomic Energy Authority began planning a decommissioning programme on the Windscale Advanced Gas Cooled Reactor after its shut down in 1981. 4 refs
Primary Subject
Source
Zaleski, C.P.; Paris-9 Univ., 75 (France); 367 p; ISBN 2-9506916-0-9; ; 1992; p. 271-280; Centre de Geopolitique de l'Energie et des Matieres Premieres; Paris (France); 3. MIEC Conference on Clean energy for Europe in transition; Paris (France); 30 Mar - 3 Apr 1992
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Book
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Conference
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AGR TYPE REACTORS, CARBON DIOXIDE COOLED REACTORS, DEMOLITION, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EUROPE, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, INDUSTRIAL PLANTS, ISOTOPE SEPARATION PLANTS, MANAGEMENT, NATIONAL ORGANIZATIONS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, UNITED KINGDOM ORGANIZATIONS, WASTE MANAGEMENT
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Johnson, A. B.
Pacific Northwest National Laboratory PNNL, Richland, WA (United States). Funding organisation: US Department of Energy (United States)2007
Pacific Northwest National Laboratory PNNL, Richland, WA (United States). Funding organisation: US Department of Energy (United States)2007
AbstractAbstract
[en] Storage of nuclear fuel after it has been discharged from reactors has become the leading spent fuel management option. Many storage facilities are being required to operate longer than originally anticipated. Aging is a term that has emerged to focus attention on the consequences of extended operation on systems, structures, and components that comprise the storage facilities. The key to mitigation of age-related degradation in storage facilities is to implement effective strategies to understand and manage aging of the facility materials. A systematic approach to preclude serious effects of age-related degradation is addressed in this paper, directed principally to smaller facilities (test and research reactors). The first need is to assess the materials that comprise the facility and the environments that they are subject to. Access to historical data on facility design, fabrication, and operation can facilitate assessment of expected materials performance. Methods to assess the current condition of facility materials are summarized in the paper. Each facility needs an aging management plan to define the scope of the management program, involving identification of the materials that need specific actions to manage age-related degradation. For each material identified, one or more aging management programs are developed and become part of the plan Several national and international organizations have invested in development of comprehensive and systematic approaches to aging management. A method developed by the US Nuclear Regulatory Commission is recommended as a concise template to organize measures to effectively manage age-related degradation of storage facility materials, including the scope of inspection, surveillance, and maintenance that is needed to assure successful operation of the facility over its required life. Important to effective aging management is a staff that is alert for evidence of materials degradation and committed to carry out the aging management programs
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1 Jul 2007; vp; NATO Advanced Research Workshop on Safety Related Issues of Spent Nuclear Fuel Storage; Almaty (Kazakhstan); 26-29 Sep 2005; AC06-76RL01830; Available from Pacific Northwest National Laboratory PNNL, Richland, WA (US); Published in: Safety Related Issues of Spent Nuclear Fuel Storage, 167-180
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Johnson, A. N.; Kraimer, M. R.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2001
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2001
AbstractAbstract
[en] The Static Database Access library was first introduced in EPICS (Experimental Physics and Industrial Control System) Release 3.11 in 1994. It provides an application program interface (API) for database configuration tools written in C to manipulate database record definitions and is used for various tasks within the core EPICS software. This paper describes the structure of a replacement for the original library that adds a native C++ API and will make some future enhancements to EPICS significantly easier to implement
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13 Nov 2001; 3 p; 8. International Conference on Accelerator and Large Experimental Physics and Control Systems (ICALEPCS 2001); San Jose, CA (United States); 27-30 Nov 2001; ISSN 0148-7191; ; W-31-109-ENG-38; Available from PURL: https://www.osti.gov/servlets/purl/792125-O9uIgV/native/
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AbstractAbstract
[en] Activities of BNFL in all stages of the nuclear fuel cycle starting from uranium ore concentrate are described
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Journal Article
Journal
Nuclear Europe; CODEN NUEUD; v. 5(1); p. 25-27
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AbstractAbstract
[en] BNFL is in a unique position in that it has commercial experience of diffusion enrichment, and of centrifuge enrichment through its associate company Urenco. In addition BNFL is developing laser enrichment techniques as part of a UK development programme in this area. The paper describes the development programme which led to the introduction of competitive centrifuge enrichment technology by Urenco and discusses the areas where improvements have and will continue to be made in the centrifuge process. It also describes the laser development programme currently being undertaken in the UK. The paper concludes by discussing the relative merits of the various methods of uranium enrichment, with particular reference to the enrichment market likely to obtain over the rest of the century. (author)
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Lu Rongguang (Chief ed.); Chinese Nuclear Society, Beijing, BJ (China); 905 p; 1987; p. 430-437; Sixth pacific basin nuclear conference; Beijing (China); 7-11 Sep 1987
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Miscellaneous
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Conference
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ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, CENTRIFUGATION, EVALUATION, EVEN-ODD NUCLEI, FLUORIDES, FLUORINE COMPOUNDS, HALIDES, HALOGEN COMPOUNDS, HEAVY NUCLEI, INDUSTRIAL PLANTS, ISOMERIC TRANSITION ISOTOPES, ISOTOPE SEPARATION, ISOTOPES, MINUTES LIVING RADIOISOTOPES, NATIONAL ORGANIZATIONS, NUCLEAR FACILITIES, NUCLEI, RADIOISOTOPES, SEPARATION PROCESSES, UNITED KINGDOM ORGANIZATIONS, URANIUM COMPOUNDS, URANIUM FLUORIDES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The Sizewell-B reactor control and instrumentation integrated systems for central operation includes three computer systems networks each based on a different computer technology. The strategy for the implementation of closed-loop control at Sizewell-B and the principles of allocation of control functions to the different computer control systems is discussed. Station Automatic control loops are important to safety and have a direct effect on the station output. Probabalistic safety assessment target reliabilities have been derived making it essential to implement the Automatic control systems within the environment of the High Integrity control system. (Author)
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Institution of Electrical Engineers, London (United Kingdom); British Nuclear Energy Society, London (United Kingdom); Institute of Energy, London (United Kingdom); Institution of Mechanical Engineers, London (United Kingdom); Convention of National Societies of Electrical Engineers of Western Europe (EUREL), London (United Kingdom); IEE Conference Publication Series; no.361; 272 p; ISBN 0 85296 550 8; ; 1992; p. 143-148; Institution of Electrical Engineers; London (United Kingdom); International conference on electrical and control aspects of the Sizewell B PWR; Cambridge (United Kingdom); 14-15 Sep 1992; ISSN 0537-9989;
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Book
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Conference
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Johnson, A.
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference2007
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference2007
AbstractAbstract
[en] This paper discusses the reactor refurbishment program at Bruce Power. The project includes re tubing, refurbishment of steam generators, turbine generators, key plant inspections, nuclear safety and licensing
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Canadian Nuclear Society, Toronto, Ontario (Canada); 303 Megabytes; ISBN 0-919784-88-7; ; 2007; [14 p.]; 28. Annual conference of the Canadian Nuclear Society and 31. CNS/CNA student conference on embracing the future: Canada's nuclear renewal and growth; Saint John, New Brunswick (Canada); 3-6 Jun 2007; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); Paper PIB001PP; Slide presentation only.
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Miscellaneous
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AbstractAbstract
[en] Central to the control and instrumentation system of the Sizewell B nuclear power plant is a control, data acquisition and control system based on a distributed network of several hundred microprocessors. The system has been integrated into a single functional unity, and software modifications affecting one part of it have an effect on the other parts. The software modification and configuration processes are therefore kept as similar as possible. (A.K.)
Original Title
Integrated Systems for Centralised Operation
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European Nuclear Society (International Organisation without Location); Czech Nuclear Society, Prague (Czech Republic); 361 p; Nov 1997; p. 53-60; International topical meeting on VVER instrumentation and control; Prague (Czech Republic); 21-24 Apr 1997; 2 figs.
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AbstractAbstract
No abstract available
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Canadian Nuclear Society, Toronto, Ontario (Canada); 159 Megabytes; ISBN 0-919784-79-8; ; 2004; [11 p.]; 25. annual CNS conference; Toronto, Ontario (Canada); 6-9 Jun 2004; Available on Compact Disc from the Canadian Nuclear Society, Toronto, Ontario (Canada); Slide presentation only.
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Miscellaneous
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AbstractAbstract
[en] A short review is given of the available experimental information as well as a discussion of some freatures of the experimental procedures. For relevant theories of nuclear rotation the reader is referred to other papers in these Proceedings. (author)
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International Centre for Theoretical Physics, Trieste (Italy); 2 v.; v. 1 p. 317-348; ISBN 9201300751; ; 1975; IAEA; Vienna; International extended seminar on nuclear physics; Trieste, Italy; 17 Sep 1973; IAEA-SMR--14/10
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