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Relevant bibliographies by topics / Gas-cooled Fast Reactor

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Academic literature on the topic 'Gas-cooled Fast Reactor'

Author: Grafiati

Published: 4 June 2021

Last updated: 16 February 2022

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Journal articles on the topic "Gas-cooled Fast Reactor"

1

Fielding, Randall, Mitch Meyer, Jan-Fong Jue, and Jian Gan. "Gas-cooled fast reactor fuel fabrication." Journal of Nuclear Materials 371, no. 1-3 (2007): 243–49. http://dx.doi.org/10.1016/j.jnucmat.2007.05.011.

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Polansky, Jiri. "Thermodynamics Cycle of Gas-Cooled Fast Reactor." Mechanics and Mechanical Engineering 22, no. 2 (2020): 585–92. http://dx.doi.org/10.2478/mme-2018-0046.

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AbstractThis paper deals with the thermo-hydraulic aspect of gas cooled fast 4 generation reactor. The paper is focused on the comparison of direct and indirect strategy of thermodynamics cycle of helium cooled reactor from the thermodynamics and turbomachinary point of view. The analyses respect pressure looses at all major part of the equipment - reactor, heat exchanger, pipe lines, etc. The compressor and gas turbines efficiency are includes in calculation as well. The working fluid in primary circuit is helium. In the secondary circuit a mixture of helium and nitrogen is considered. The Cy

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3

Stainsby, Richard, Karen Peers, Colin Mitchell, Christian Poette, Konstantin Mikityuk, and Joe Somers. "Gas cooled fast reactor research in Europe." Nuclear Engineering and Design 241, no. 9 (2011): 3481–89. http://dx.doi.org/10.1016/j.nucengdes.2011.08.005.

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Hejzlar, Pavel, Michael J. Pope, Wesley C. Williams, and Michael J. Driscoll. "Gas cooled fast reactor for generation IV service." Progress in Nuclear Energy 47, no. 1-4 (2005): 271–82. http://dx.doi.org/10.1016/j.pnucene.2005.05.077.

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Gužela, Štefan, František Dzianik, Martin Juriga, and Juraj Kabát. "Shell and Tube Heat Exchanger – the Heat Transfer Area Design Process." Strojnícky casopis – Journal of Mechanical Engineering 67, no. 2 (2017): 13–24. http://dx.doi.org/10.1515/scjme-2017-0014.

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AbstractNowadays, the operating nuclear reactors are able to utilise only 1 % of mined out uranium. An effective exploitation of uranium, even 60 %, is possible to achieve in so-called fast reactors. These reactors commercial operation is expected after the year 2035. Several design configurations of these reactors exist. Fast reactors rank among the so-called Generation IV reactors. Helium-cooled reactor, as a gas-cooled fast reactor, is one of them. Exchangers used to a heat transfer from a reactor active zone (i.e. heat exchangers) are an important part of fast reactors. This paper deals wi

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van Rooijen, W. F. G. "Gas-Cooled Fast Reactor: A Historical Overview and Future Outlook." Science and Technology of Nuclear Installations 2009 (2009): 1–11. http://dx.doi.org/10.1155/2009/965757.

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A review is given of developments in the area of Gas-Cooled Fast Reactors (GCFR) in the period from roughly 1960 until 1980. During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants. During this period, the GCFR concept was found to be more challenging than liquid-metal-cooled reactors, and none were ever constructed. In the second part of the paper, we provide an overview of the investigations on GCFR since the year 2000, when the Generation IV Init

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Zaki, Su'ud. "Unprotected Loss of Flow Accident in Small Long Life Gas Cooled Fast Reactor." Applied Mechanics and Materials 751 (April 2015): 263–67. http://dx.doi.org/10.4028/www.scientific.net/amm.751.263.

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In post Fukushima nuclear accidents inherent safety capability is necessary against some standard accidents such as unprotected loss of flow (ULOF), unprotected rod run-out transient over power (UTOP), unprotected loss of heat sink (ULOHS). Gas cooled fast reactors is one of the important candidate of 4th generation nuclear power plant and in this paper the safety analysis related to unprotected loss of flow in small long life gas cooled fast reactors has been performed. Accident analysis of unprotected loss of flow include coupled neutronic and thermal hydraulic analysis which include adiabat

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Monado, Fiber, Zaki Su’ud, Abdul Waris, Khairul Basar, Menik Ariani, and Hiroshi Sekimoto. "Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor." Advanced Materials Research 772 (September 2013): 501–6. http://dx.doi.org/10.4028/www.scientific.net/amr.772.501.

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Gas-cooled Fast Reactor is a good candidate for fourth generation nuclear power plant that projected to be used started in 2030. In this study, modified CANDLE burn-up strategy is adopted to create 300 MWt long life Gas-cooled Fast Reactor with metallic fuel U-10wt%Zr without enrichment. This design demonstrated excellent performance with the average discharge burn-up is about 25.9% HM.

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Kvizda, Boris, Gusztáv Mayer, Petr Vácha, et al. "ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark." Nuclear Engineering and Design 345 (April 2019): 47–61. http://dx.doi.org/10.1016/j.nucengdes.2019.02.006.

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Perkó, Zoltán, Sandro Pelloni, Konstantin Mikityuk, et al. "Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor." Progress in Nuclear Energy 83 (August 2015): 460–81. http://dx.doi.org/10.1016/j.pnucene.2014.09.016.

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Dissertations / Theses on the topic "Gas-cooled Fast Reactor"

1

Nuwayhid, Rida Y. "Assessment of thermal and fast reactor designs based upon the advance gas-cooled reactor." Thesis, Imperial College London, 1989. http://hdl.handle.net/10044/1/47595.

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Yarsky, Peter. "Core design and reactor physics of a breed and burn gas-cooled fast reactor." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/34650.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.<br>Includes bibliographical references (p. 245-248).<br>In order to fulfill the goals set forth by the Generation IV International Forum, the current NERI funded research has focused on the design of a Gas-cooled Fast Reactor (GFR) operating in a Breed and Burnm (B&B) fuel cycle mode. B&B refers to a once-through fuel cycle where low enriched uranium (less than 5 w/o 235U in U) subcritical assemblies are loaded into the core in equilibrium, yet in-situ plutonium breeding carries the fuel through a disch

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Delaney, Michael J. (Michael James) 1979. "Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/17747.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.<br>Includes bibliographical references (p. 75-77).<br>Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, an advanced reactor's core damage frequency dominates all other considerations at the preliminary stage of reactor design. An iterative four-step methodology to guide the MIT gas-cooled fast reactor emergency core cooling system desi

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Jourdan, Grégoire. "Using risk-based regulations for licensing nuclear power plants : case study of gas-cooled fast reactor." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/32278.

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Thesis (S.M.)--Massachusetts Institute of Technology, Engineering Systems Division, Technology and Policy Program, 2005.<br>Includes bibliographical references (p. 78-82).<br>The strategy adopted for national energy supply is one of the most important policy choice for the US. Although it has been dismissed in the past decades, nuclear power today has key assets when facing concerns on energy dependence and global warming. However, reactor licensing regulations need to be changed to get all the advantages of the most promising technologies. After reviewing the well-known drawbacks of the curre

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Cochran, Peter A. (Peter Andrew). "Design of an experimental loop for post-LOCA heat transfer regimes in a Gas-cooled Fast Reactor." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/34456.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.<br>Includes bibliographical references.<br>The goal of this thesis is to design an experimental thermal-hydraulic loop capable of generating accurate, reliable data in various convection heat transfer regimes for use in the formulation of a comprehensive convection heat transfer correlation. The initial focus of the design is to ensure that the loop will be able to generate the convection flow regimes found in post Loss of Coolant Accident (LOCA) operation of a Gas-cooled Fast Reactor (GFR). As a result a

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Gezelius, Knut 1978. "Design of compact intermediate heat exchangers for gas cooled fast reactors." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/26911.

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Thesis (S.M. and S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.<br>Includes bibliographical references (p. 171-174).<br>Two aspects of an intermediate heat exchanger (IHX) for GFR service have been investigated: (1) the intrinsic characteristics of the proposed compact printed circuit heat exchanger (PCHE); and (2) a specific design optimizing economic and technical efficiency while coupling a supercritical CO2 Brayton power cycle to a helium cooled fast reactor core. In particular, the wavy channel friction factor and the effective conduction thickness betwe

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Bes, René. "Comportement thermique du xénon dans le nitrure de titane fritté matrice inerte d’intérêt des RNR-G." Thesis, Lyon 1, 2010. http://www.theses.fr/2010LYO10227/document.

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Ce travail se place dans le cadre des réacteurs nucléaires de 4ème génération tels que les réacteurs à neutrons rapides et caloporteur gaz (RNR-G), pour lesquels des matériaux réfractaires comme le nitrure de titane (TiN) enroberont le combustible afin de permettre la rétention des produits de fission. Cette étude a porté sur le comportement thermique intragranulaire du xénon dans des échantillons de TiN obtenus par frittage à chaud sous charge. Le rôle de la microstructure sur le comportement thermique du xénon a été étudié. Plusieurs lots ont ainsi été synthétisés sous différentes conditions

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Gutierrez, Gaëlle. "Étude du comportement thermique et sous irradiation du xénon dans l’oxycarbure de zirconium." Thesis, Lyon 1, 2011. http://www.theses.fr/2011LYO10276/document.

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Les réacteurs GEN IV (GFR) nécessitent l’emploi de matériaux d’enrobage ayant une bonne transparence aux neutrons, une conductivité thermique élevée et agissant comme barrière de diffusion pour les produits de fission. Le but de cette étude est de déterminer le rôle de la température et de l’irradiation sur le comportement du xénon implanté dans l’oxycarbure de zirconium (ZrCxOy). A cet effet, des poudres de deux stoechiométries ZrC0,95O0,05 et ZrC0,8O0,2 ont été synthétisées puis frittées par frittage flash, ou sous charge. Pour étudier le rôle de la fluence d’implantation sur la migration th

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Kumar, Mithlesh. "Magnetic flux distorsion in two-phase liquid metal flow." Phd thesis, Toulouse, INPT, 2016. http://oatao.univ-toulouse.fr/15854/1/Kumar_1.pdf.

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A Generation IV Sodium cooled Fast Reactor (SFR) is being researched and developed at CEA, Cadarache France under the project named ASTRID. Monitoring gas presence in SFR is important with respect to its safe operation. In accordance with the principles of diversity, techniques based on different measurement principles have been proposed. This thesis concerns the detection and characterization of void using magnetic flux perturbation principle. An Eddy Current Flow Meter (ECFM) device is used for this purpose. From the technological point of view, the objective is to evaluate the feasibility o

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Books on the topic "Gas-cooled Fast Reactor"

1

Willem Frederik Geert van Rooijen. Improving fuel cycle design and safety characteristics of a gas cooled fast reactor. IOS Press, 2006.

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2

Glushkov, Evgeniĭ Serafimovich. Razrabotka bystrykh gazookhlazhdaemykh reaktorov v Rossii. IzdAT, 2008.

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Glushkov, Evgeniĭ Serafimovich. Razrabotka bystrykh gazookhlazhdaemykh reaktorov v Rossii. IzdAT, 2008.

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Book chapters on the topic "Gas-cooled Fast Reactor"

1

Taylor, J'tia P. "Generation-IV Gas-Cooled Fast Reactor." In Nuclear Energy Encyclopedia. John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch29.

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Rui, Han, and Chen Shu-ming. "Sodium-Cooled Fast Breed Reactor Fuel Failure Detection Based on Cover Gas Monitoring." In Proceedings of The 20th Pacific Basin Nuclear Conference. Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2314-9_79.

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Weaver, Kevan. "Gas-Cooled Fast Reactors." In Fast Spectrum Reactors. Springer US, 2011. http://dx.doi.org/10.1007/978-1-4419-9572-8_17.

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Kohyama, Akira. "Advanced SiC/SiC Composite Materials for Fourth Generation Gas Cooled Fast Reactors." In Key Engineering Materials. Trans Tech Publications Ltd., 2005. http://dx.doi.org/10.4028/0-87849-965-2.16.

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5

"Chapter 11. The gas-cooled fast reactor." In Nuclear Reactor Systems. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1985-0-014.

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"Chapter 11. The gas-cooled fast reactor." In Nuclear Reactor Systems. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1985-0.c014.

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Hatala, Branislav. "Gas Cooled Fast Reactor System (GFR)." In Reference Module in Earth Systems and Environmental Sciences. Elsevier, 2020. http://dx.doi.org/10.1016/b978-0-12-409548-9.12207-9.

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Tsvetkov, P. "Gas-cooled fast reactors." In Handbook of Generation IV Nuclear Reactors. Elsevier, 2016. http://dx.doi.org/10.1016/b978-0-08-100149-3.00004-5.

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Chauvin, N. "Fuels for Fast-Spectrum Gas-Cooled Reactors." In Encyclopedia of Materials: Science and Technology. Elsevier, 2011. http://dx.doi.org/10.1016/b978-0-08-043152-9.02265-x.

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Conference papers on the topic "Gas-cooled Fast Reactor"

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Joseph, Jofred, Satish Kumar, Tanmay Vasal, and N. Theivarajan. "Brayton Cycle As an Alternate Power Conversion Option for Sodium Cooled Fast Reactor." In ASME 2019 Gas Turbine India Conference. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/gtindia2019-2455.

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Abstract Enhancing the safety and economic competitiveness are major objectives in the development of advanced reactor designs with emphasis on the design of systems or components of the nuclear systems. Innovative power cycle development is another potential option to achieve these objectives. Sodium cooled fast reactor (SFR) is one among the six reactor design concepts identified by the Gen IV International Forum for development to meet the technology goals for new nuclear energy system. Similar to the power cycle used in conventional fossil fuel based thermal power plants, sodium-cooled fas

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Dostal, Vaclav, Michael J. Driscoll, Pavel Hejzlar, and Yong Wang. "Supercritical CO2 Cycle for Fast Gas-Cooled Reactors." In ASME Turbo Expo 2004: Power for Land, Sea, and Air. ASMEDC, 2004. http://dx.doi.org/10.1115/gt2004-54242.

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Brayton cycles are currently being extensively investigated for possible use with nuclear reactors in order to reduce capital cost, shorten construction period and increase nuclear power plant efficiency. The main candidates are the well-known helium Brayton cycle and the less familiar supercritical CO2 cycle, which has been given increased attention in the past several years. The main advantage of the supercritical CO2 cycle is comparable efficiency with the helium Brayton cycle at significantly lower temperature (550°C/823K), but higher pressure (20MPa/200 normal atmospheres). By taking adva

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Cheng, Lap Y., Hans Ludewig, and Jae Jo. "Emergency Decay Heat Removal in a GEN-IV Gas-Cooled Fast Reactor." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89681.

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A series of transient analyses using the system code RELAP5-3d has been performed to confirm the efficacy of a proposed hybrid active/passive combination approach to the decay heat removal for an advanced 2400MWt GEN-IV gas-cooled fast reactor. The accident sequence of interest is a station blackout simultaneous with a small break (10 sq.inch/0.645m2) in the reactor vessel. The analyses cover the three phases of decay heat removal in a depressurization accident: (1) forced flow cooling by the power conversion unit (PCU) coast down, (2) active forced flow cooling by a battery powered blower, an

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Monado, Fiber, Zaki Su'ud, Abdul Waris, Khairul Basar, Menik Ariani, and Hiroshi Sekimoto. "Power flattening on modified CANDLE small long life gas-cooled fast reactor." In 4TH INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING (ICANSE 2013). AIP Publishing LLC, 2014. http://dx.doi.org/10.1063/1.4895859.

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Drajat, R. Z., Z. Su'ud, E. Soewono, and A. Y. Gunawan. "Multi channel thermal hydraulic analysis of gas cooled fast reactor using genetic algorithm." In THE 5TH INTERNATIONAL CONFERENCE ON RESEARCH AND EDUCATION IN MATHEMATICS: ICREM5. AIP, 2012. http://dx.doi.org/10.1063/1.4724148.

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Polanský, Jiří, and Roman Gášpár. "Optimization of the Thermodynamics Cycles of Generation IV Gas-Cooled Fast Reactors." In ASME 2013 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/imece2013-64565.

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This paper deals with the thermo-hydraulic properties of Generation IV Gas Cooled Fast Reactors. The paper is focused on the comparison of direct and indirect thermodynamic cycles of helium cooled reactors from a thermodynamic point of view. The calculation includes pressure losses at all major parts of the equipment — reactor, heat exchangers, pipe lines, etc. The compressor and the gas turbine efficiencies are included in calculation as well. The working fluid used in the primary circuit is helium. In the secondary circuit a mixture of helium and nitrogen is used. The cycle characteristic po

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Lewis, Tom G., Edward J. Parma, Steven A. Wright, Milton E. Vernon, Darryn D. Fleming, and Gary E. Rochau. "Sandia’s Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR) Concept." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6612.

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The advanced nuclear concept group at Sandia National Laboratories has been investigating two advance right size reactors (RSR); this paper will discuss one of these two systems. The supercritical carbon dioxide (S-CO2), direct cycle gas fast reactor (SC-GFR) concept was developed to determine the feasibility of a RSR type concept using S-CO2 as the working fluid in a direct cycle fast reactor. Although a significant amount of work is still required, this type of reactor concept maintains some potentially significant advantages over ideal gas-cooled systems and liquid metal-cooled systems. The

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Raflis, H., Z. Su’ud, A. Waris, D. Irwanto, and N. Takaki. "Core depletion analysis of long-life CANDLE gas-cooled fast reactor using OpenMC code." In PROCEEDINGS OF THE 6TH INTERNATIONAL SYMPOSIUM ON CURRENT PROGRESS IN MATHEMATICS AND SCIENCES 2020 (ISCPMS 2020). AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0058906.

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Dragunov, Alexey, Eugene Saltanov, Igor Pioro, Brian Ikeda, Marija Miletic, and Anastasiia Zvorykina. "Investigation of Thermophysical and Nuclear Properties of Prospective Coolants for Generation-IV Nuclear Reactors." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16020.

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Recently, a group of countries has initiated an international collaboration, the Generation IV International Forum (GIF), to develop the next-generation nuclear reactors. The GIF program has narrowed the design options of nuclear reactors to the following six concepts: 1) SuperCritical-Water-cooled Reactor (SCWR); 2) Sodium-cooled Fast Reactor (SFR); 3) Lead-cooled Fast Reactor (LFR); 4) Molten Salt Reactor (MSR); 5) Gas-cooled Fast Reactor (GFR); and 6) Very-High-Temperature Reactor (VHTR); The purpose of this paper is to compare main thermophysical, corrosion, and neutronic properties of the

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Ohshima, Hiroyuki, and Takemitsu Nagata. "Numerical Study on Thermal Hydraulics in Coated-Particle-Type Fuel Assembly of Helium Gas Cooled Fast Reactor." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49186.

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A helium-gas-cooled fast reactor with coated-particle-type fuel is being examined as a candidate of commercialized fast reactors at Japan Nuclear Cycle Development Institute. As one of characteristics of this reactor design, coolant passes through coated particle fuel regions of fuel assemblies “laterally” to reduce pressure loss. From the viewpoint of coolability and structure integrity of the fuel assembly, it should be confirmed that the coolant keeps flowing through the fuel regions laterally and uniformly to remove heat from the fuel particles properly under various operating conditions.

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Reports on the topic "Gas-cooled Fast Reactor"

1

K. D. Weaver, T. Marshall, T. Totemeier, et al. Gas-Cooled Fast Reactor (GFR) FY05 Annual Report. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/911777.

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K. D. Weaver, T. C. Totemeier, D. E. Clark, et al. Gas-Cooled Fast Reactor (GFR) FY04 Annual Report. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/911236.

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Gougar, Hans D. Gas-cooled Fast Reactor Research and Development Roadmap. Office of Scientific and Technical Information (OSTI), 2017. http://dx.doi.org/10.2172/1484712.

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Gougar, Hans D. Gas-cooled Fast Reactor Research and Development Roadmap. Office of Scientific and Technical Information (OSTI), 2018. http://dx.doi.org/10.2172/1599068.

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CHENG, L. Y., and H. LUDEWIG. 2400MWt GAS-COOLED FAST REACTOR DHR STUDIES STATUS UPDATE. Office of Scientific and Technical Information (OSTI), 2007. http://dx.doi.org/10.2172/910926.

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K. D. Weaver, L-Y. Cheng, H. Ludewig, and J. Jo. Gas-Cooled Fast Reactor (GFR) Decay Heat Removal Concepts. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/911253.

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Cheng, L. Y., and H. Ludewig. ATWS Transients for the 2400 MWt Gas-Cooled Fast Reactor. Office of Scientific and Technical Information (OSTI), 2007. http://dx.doi.org/10.2172/941620.

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Kevan D. Weaver. Interim Status Report on the Design of the Gas-Cooled Fast Reactor (GFR). Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/911014.

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Weaver, K. D. Interim Status Report on the Design of the Gas-Cooled Fast Reactor (GFR). Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/862023.

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Belles, Randy, Willis P. Poore, III, Nicholas R. Brown, et al. Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors. Office of Scientific and Technical Information (OSTI), 2017. http://dx.doi.org/10.2172/1361360.

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