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Author : P. Fortescue
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (9 download)
Download or read book Thermodynamic Aspects of Coolant Choice for Gas Cooled Reactors written by P. Fortescue and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Oak Ridge National Laboratory
Publisher :
ISBN 13 :
Total Pages : 32 pages
Book Rating : 4.3/5 (91 download)
Download or read book Gas-cooled Reactor Coolant Choice written by Oak Ridge National Laboratory and published by . This book was released on 1959 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermodynamic Data for Selected Gas Impurities in the Primary Coolant of High-temperature Gas-cooled Reactors written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 478 pages
Book Rating : 4.3/5 (91 download)
Download or read book Evaluation of Coolants and Moderators for the Maritime Gas-cooled Reactor written by and published by . This book was released on 1958 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. C. Holmes
Publisher :
ISBN 13 :
Total Pages : 56 pages
Book Rating : 4.3/5 (91 download)
Download or read book A Preliminary Evaluation of Gas Cooling of Power Reactors Moderated by Heavy Water written by R. C. Holmes and published by . This book was released on 1958 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. H. Armstrong
Publisher :
ISBN 13 :
Total Pages : 60 pages
Book Rating : 4.:/5 (319 download)
Download or read book Gas-cooled Reactors in the USA written by R. H. Armstrong and published by . This book was released on 1960 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study was made of approximately 132 reports on gas-cooled reactors and related subjects. Charts and tables containing the following information are included: all available reactor information, reactor flow diagrams of suggested concepts, possible core arrangement at core cross section, typical fuel and moderator cell, possible fuel types for unit fuel cell, the properties of materials for moderators and reflectors. the compatibility of gases and base fuel materials at maximum surface temperatures, maximum interface temperatures of fuel elements and core-jacket combinations, allowable operating temperatures and compatibility of gases and various metals. preferences for gas coolants, cost and availability of gases plant thermal cycle efficiencies, thermal properties of gases, pumping power and reactor coolant inlet temperatures, obtainable heat fluxes, composition and physical properties of potential cladding materials. atomic and thermal properties of cladding materials, fabrication characteristics and costs of cladding materials, possible process applications of gases at high temperature, and potential high-temperature materials. The various categories of gas-cooled reactors and examples of each type are discussed. A gas reactor program for high-temperature experimentation is proposed.
Author : United States. Congress. Joint Committee on Atomic Energy
Publisher :
ISBN 13 :
Total Pages : 102 pages
Book Rating : 4.F/5 ( download)
Download or read book Technical Aspects of the Report on the Gas-cooled, Graphite-moderated Reactor written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1958 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Willem Frederik Geert van Rooijen
Publisher : IOS Press
ISBN 13 : 9781586036966
Total Pages : 160 pages
Book Rating : 4.0/5 (369 download)
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Download or read book GAS COOLED POWER REACTOR COOLANT CHOICE. written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The current status of helium and carbon dioxide technology is described in the light of the Gas Cooled Reactor Program requiremoents. The problem of containing high-pressure helium at high temperature is discussed, and it is concluded that, by proper attention to the design, construction and maintenance of a plant, a high degree of helium leak-tightness can be achieved at small additional cost when compared with a carbon dioxide system. What is more, the cost of making up helium losses in a practically achievable system is estimated to be small compared with other fixed and operating costs. Graphite-carbon dioxide reaction data are reviewed. It is shown that carbon dioxide at atmospheric pressure and low flow rates should be compatible with a graphite mooderator up to 525 C. No data are available at the high pressures and fiow rates that would be encountered in power reactors. Significantiy higher oxidation rates may result, however, perhaps limiting bulk moderator temperatures to 450 to 500 C. Improved carbon materials, protective coatings and inhibitors, and/or operating practices may be developed that will allow significant future increases in these limiting temperatures. (auth).
Author :
Publisher :
ISBN 13 :
Total Pages : 74 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fuel Breeding written by and published by . This book was released on 1959 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 680 pages
Book Rating : 4.E/5 ( download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Massoud T. Simnad
Publisher : Gordon & Breach Publishing Group
ISBN 13 :
Total Pages : 646 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fuel Element Experience in Nuclear Power Reactors written by Massoud T. Simnad and published by Gordon & Breach Publishing Group. This book was released on 1971 with total page 646 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 80 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reactor Safety written by and published by . This book was released on 1971 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Alexey Dragunov
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (13 download)
Download or read book Development of Thermodynamic Cycles for Sodium-cooled-fast Reactors written by Alexey Dragunov and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Aleksandr Efimovich Sheĭndlin
Publisher : CRC Press
ISBN 13 : 9780891165682
Total Pages : 424 pages
Book Rating : 4.1/5 (656 download)
Download or read book High Temperature Equipment written by Aleksandr Efimovich Sheĭndlin and published by CRC Press. This book was released on 1986-08-01 with total page 424 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 720 pages
Book Rating : 4.E/5 ( download)
Download or read book TID. written by and published by . This book was released on 19?? with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : International Atomic Energy Agency
Publisher :
ISBN 13 :
Total Pages : 96 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reactor Coolant and Associated Systems in Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: Covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems.
