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AbstractAbstract
[en] Papers are arranged under the following topical sections: Gas turbine combustion; Advanced energy conversion; Low NOx solutions; Burner developments; Alternative fuels combustion; Advanced energy conversion technologies; Numerical modeling of combustion; Fluidized bed combustion; Coal combustion; Combustion research; Gasification systems; Mercury emissions; Highly preheated air combustion; Selective catalytic reduction; Special topics in combustion research; Gas turbines and advanced energy; and How can the nuclear industry become more efficient? Papers within scope have been processed separately for inclusion on the database
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1999; 651 p; American Society of Mechanical Engineers; New York, NY (United States); 1999 International Joint Power Generation Conference; Burlingame, CA (United States); 25-28 Jul 1999; ISBN 0-7918-1614-1; ; Also available from American Society of Mechanical Engineers, Three Park Avenue, New York, NY 10016 (US); $120.00
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Book
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Conference
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ABSTRACTS, CARBONACEOUS MATERIALS, CHALCOGENIDES, CHEMICAL REACTION KINETICS, ENERGY SOURCES, EQUIPMENT, FLUIDS, FOSSIL FUELS, FUEL GAS, FUELS, GAS FUELS, GASES, HEATERS, KINETICS, MACHINERY, MATERIALS, NITROGEN COMPOUNDS, NUCLEAR FACILITIES, OXIDES, OXYGEN COMPOUNDS, POLLUTION ABATEMENT, POWER PLANTS, REACTION KINETICS, SOLID FUELS, THERMAL POWER PLANTS, TURBINES, TURBOMACHINERY
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AbstractAbstract
[en] Nuclear energy is discussed for applications beyond electrical production. To explore that potential, a series of investigations addressing the process heat market and the High-Temperature Gas-Cooled Reactor (HTGR) were conducted. A substantial technical and economic potential has been identified for a steam cycle HTGR operating in a cogeneration mode. 8 refs
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IECEC conference; Atlanta, GA (USA); 9 - 14 Aug 1981; CONF-810812--
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Journal Article
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Conference
Journal
Proceedings, Intersociety Energy Conversion Engineering Conference; ISSN 0146-955X; ; v. 3 p. 2198-2203
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Kasten, P.R.; Neylan, A.J.; Penfield, S.R. Jr.
Oak Ridge National Lab., TN (USA); GA Technologies, Inc., San Diego, CA (USA); Gas-Cooled Reactor Associates, San Diego, CA (USA)1985
Oak Ridge National Lab., TN (USA); GA Technologies, Inc., San Diego, CA (USA); Gas-Cooled Reactor Associates, San Diego, CA (USA)1985
AbstractAbstract
[en] Several concepts are being evaluated in the US HTR Program to explore designs which might improve the commercial viability of nuclear power. The general approach is to reduce the reactor power and increase the ability to use inherent features for removing heat following extreme accidents. The unit size and design of these concepts are constrained so that extreme accidents do not result in significant release of radioactivity from the reactor plant. Through the greater reliance on inherent safety features in small HTRs, it should be possible to minimize the amount of nuclear grade components required in the balance-of-plant, which could lead to an economic system. Four HTR concepts are presently being evaluated within the US Program, and these concepts are briefly summarized. A modular HTR using a steel pressure vessel, which is very similar to one of the four HTR concepts being evaluated within the US National program, is presented as an example of a specific concept to illustrate the features and performance of HTRs having a high degree of inherent safety
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Aug 1985; 27 p; Japan Atomic Energy Research Institute annual open seminar on research and development of the multipurpose VHTR; Tokyo (Japan); 12 Dec 1984; DOE/HTGR--85-082; CONF-841287--1; Available from NTIS, PC A03/MF A01 as DE86001464
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Report
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Penfield, S.R. Jr.; Hayes, R.H.; McMullen, R.
North American Electric Reliability Council, Princeton, NJ (United States)1999
North American Electric Reliability Council, Princeton, NJ (United States)1999
AbstractAbstract
[en] Papers are arranged under the following topical sections: Benefits of software application in plant optimization; Combined cycle power plants; Recent improvements in power generation operations; Efficiency and capacity improvements for steam turbines; Condenser and heat exchange performance and fouling; Performance testing, monitoring and evaluation; Steam turbine/generator system--maintance, life assesments and upgrades; System design evaluations; Steam generators; Turbines for combined cycle and cogeneration; Case studies on steam turbine/generator problems and solutions; Condenser and feedwater heater operation and maintenance; Risked based and reliability programs for plant applications; Improving operating flexibility of steam turbine/generators (minimizing startup time, load changing, etc.); New techniques and innovations in heat transfer systems; Case studies in reliability based maintenance; and Risk analysis applied to steam turbine/generator systems. Papers within scope have been processed separately for inclusion on the database
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1999; 752 p; American Society of Mechanical Engineers; New York, NY (United States); 1999 International Joint Power Generation Conference; Burlingame, CA (United States); 25-28 Jul 1999; ISBN 0-7918-1615-X; ; Also available from American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017 (US) $200.00
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Book
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Conference
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Spellman, D.J.; McMain, A.T. Jr.; Penfield, S.R. Jr.
Gas-Cooled Reactor Associates, La Jolla, CA (USA)1981
Gas-Cooled Reactor Associates, La Jolla, CA (USA)1981
AbstractAbstract
[en] In considering the potential of the HTGR for nuclear cogeneration, a logical element for investigation is the recent history of nuclear cogeneration experience. Little is found in recent literature; however, the twin nuclear cogeneration plant at Midland is nearing completion and this milestone will no doubt be the basis for a number of reports on the unique cogeneration facility and operating experiences with it. Less well known in the US is the Bruce Nuclear Power Development in Ontario, Canada. Originally designed to cogenerate steam for heavy water production, the Bruce facility is the focus of a major initiative to create an energy park on the shores of Lake Huron. To obtain an improved understanding of the status and implications of current nuclear cogeneration experience, GCRA representatives visited the Ontario Hydro offices in Toronto and subsequently toured the Midland site near Midland, Michigan. The primary purpose of this report is to summarize the results of those visits and to develop a series of conclusions regarding the implications for HTGR cogeneration concepts
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2 Dec 1981; 63 p; Available from NTIS, PC A04/MF A01; 1 as DE83008098
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Report
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CANDU TYPE REACTORS, COOLING SYSTEMS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, NATURAL URANIUM REACTORS, OPERATION, PHWR TYPE REACTORS, POWER GENERATION, POWER REACTORS, PRESSURE TUBE REACTORS, PROCESS HEAT REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
[en] The High Temperature Gas-Cooled Reactor (HTGR) provides a basis for expanding the role of nuclear energy into the transportation and direct heat energy sectors, in the former through synthetic fuels programs and in the latter through industrial process heat. This additional potential for the HTGR is founded upon its high temperature capabilities, unique among current nuclear concepts. In addition to allowing direct competition with fossil fuels, the high temperature capabilities of the HTGR allow consideration of energy storage and distribution concepts based upon sensible heat and latent chemical energy. 7 refs
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15. intersociety energy conversion engineering conference; Seattle, WA, USA; 18 - 22 Aug 1980; CONF-800806--
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Journal Article
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Proceedings, Intersociety Energy Conversion Engineering Conference; v. 2 p. 1091-1096
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Penfield, S.R. Jr.
Gas-cooled reactors today. (Vol.4). Papers. Discussion. Closing address. Corrigenda1983
Gas-cooled reactors today. (Vol.4). Papers. Discussion. Closing address. Corrigenda1983
AbstractAbstract
[en] a summary of progress in the U.S. HTGR Program from the perspective of utilities and energy users is given. Major points of discussion include the increasingly favorable experience at Fort St. Vrain, progress in the development of the HTGR-Steam Cycle/Cogeneration Lead Plant design, and an overview of the Utility/User proposal for Lead Plant deployment. (author)
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British Nuclear Energy Society, London; p. 103-110; ISBN 07277 0169 X (COMPLETE SET); ; 1983; p. 103-110; British Nuclear Energy Society; London (UK); Symposium on gas-cooled reactors today; Bristol (UK); 20-24 Sep 1982; Available from B.N.E.S., 1-7 Great George St., London SW1P 3AA
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Book
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AbstractAbstract
[en] In the ''matrix'' steam generator, sodium and water flow in separate tubes which are in close proximity in the region of heat transfer. In order to facilitate heat transfer, a high thermal conductivity matrix material occupies the space between tubes. Thermal contact between tubing and matrix is provided by a fluid ''shim.'' Results of thermal size calculations are presented which suggest screening criteria for selection of matrix and shim materials. Based on a survey of possible tubing, matrix, and shim materials, a compatible combination (2$one quarter$ Cr-1 Mo tubing, graphite matrix, lead-bismuth shim) was selected which satisfies the thermal size criteria. The resulting steam generator eliminates the possibility of a sodium water reaction under normal circumstances and offers a number of additional operating advantages. 10 refs
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Journal Article
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Am. Soc. Mech. Eng., [Pap.]; (76-jpgc-ne-8); p. 1-8
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ALKALI METALS, ALLOYS, BOILERS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, ELEMENTS, ENERGY TRANSFER, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HYDROGEN COMPOUNDS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, METALS, MOLYBDENUM ALLOYS, OXYGEN COMPOUNDS, REACTORS, STEELS, TRANSITION ELEMENT ALLOYS, VAPOR GENERATORS
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Penfield, S.R. Jr.; Gotschall, H.L.
2nd ASME-JSME international conference on nuclear engineering -- 19931993
2nd ASME-JSME international conference on nuclear engineering -- 19931993
AbstractAbstract
[en] This paper describes the current status of the US Modular High-Temperature Gas-Cooled Reactor (MHTGR) Program and the prospects for its further advancement. Key topics include the structure of the MHTGR Program, a description of the reactor and power conversion technologies being developed and the present status of licensing, economic assessments and deployment strategy issues
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Peterson, P.F. (ed.) (Univ. of California, Berkeley, CA (United States)); 914 p; ISBN 0-7918-0637-5; ; 1993; p. 617-625; American Society of Mechanical Engineers (ASME); New York, NY (United States); 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering; San Francisco, CA (United States); 21-24 Mar 1993; American Society of Mechanical Engineers, 345 East 47th Street, New York, NY 10017 (United States)
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Penfield, S.R. Jr.; Goodjohn, A.J.
Proceedings of the 22nd intersociety energy conversion engineering conference1987
Proceedings of the 22nd intersociety energy conversion engineering conference1987
AbstractAbstract
[en] This paper summarizes a market assessment which addresses the market potential for the Modular High Temperature Gas Cooled Reactor (MHTGR). It was found that, while current projections indicate a need for additional electric generation capacity, uncertainty with respect to projections and the evolving institutional framework constitute major barriers. The MHTGR, which was designed to utility requirements reflecting the current institutional environment, provides a technical basis to address such issues. The assessment also found substantial market potential for the MHTGR in the U.S. industrial sector and in international markets, where the smaller size of the MHTGR increases its compatibility relative to larger HTGR systems
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Anon; p. 1555-1562; 1987; p. 1555-1562; American Institute Aeronaut and Astronaut; New York, NY (USA); 22. intersociety energy conversion engineering conference; Philadelphia, PA (USA); 10-14 Aug 1987
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