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Fuel Development For Gas-Cooled Fast Reactors

Description: The Generation IV Gas-cooled Fast Reactor (GFR) concept is proposed to combine the advantages of high-temperature gas-cooled reactors (such as efficient direct conversion with a gas turbine and the potential for application of high-temperature process heat), with the sustainability advantages that are possible with a fast-spectrum reactor. The latter include the ability to fission all transuranics and the potential for breeding. The GFR is part of a consistent set of gas-cooled reactors that in… more
Date: June 1, 2006
Creator: Meyer, M. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor

Description: Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety over present day nuclear reactors. Accurate simulation models of these Generation IV reactors are necessary for design and licensing. One design under consideration by the Very High Temperature Reactor (VHTR) program is a modular, prismatic gas-cooled reactor. In this reactor, the lower plenum region may experience locally high temperatures that can adversely impact the plant’s structural integri… more
Date: November 1, 2006
Creator: Guillen, Donna Post
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CFD Analysis of Turbulent Flow Phenomena in the Lower Plenum of a Prismatic Gas-Cooled Reactor

Description: This paper is concerned with the implementation of a computational model of turbulent flow in a section of the lower plenum of Very High Temperature Reactor (VHTR). The proposed model has been encoded in a state-of-the-art CFD code, NPHASE. The results of NPHASE predictions have been compared against the experimental data collected using a scaled model of a sub-region in the lower plenum of a modular prismatic gas-cooled reactor. It has been shown that the NPHASE-based model is capable of predi… more
Date: September 1, 2007
Creator: Gallaway, T.; Antal, S.P.; Podowski, M.Z. & Guillen, D.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel Summary for Peach Bottom Unit 1 High-Temperature Gas-Cooled Reactor Cores 1 and 2

Description: This fuel summary report contains background and summary information for the Peach Bottom Unit 1, High-Temperature, Gas-Cooled Reactor Cores 1 and 2. This report contains detailed information about the fuel in the two cores, the Peach Bottom Unit 1 operating history, nuclear parameters, physical and chemical characteristics, and shipping and storage canister related data. The data in this document have been compiled from a large number of sources and are not qualified beyond the qualification o… more
Date: April 1, 2003
Creator: Kingrey, Karel I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Configurations and Coupling High Temperature Gas-Cooled Reactor and Hydrogen Plant

Description: The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power … more
Date: April 1, 2008
Creator: Oh, Chang H.; Kim, Eung Soo & Sherman, Steven
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Initial assessment of environmental effects on SiC/SiC composites in helium-cooled nuclear systems

Description: This report summarized the information available in the literature on the chemical reactivity of SiC/SiC composites and of their components in contact with the helium coolant used in HTGR, VHTR and GFR designs. In normal operation conditions, ultra-high purity helium will have chemically controlled impurities (water, oxygen, carbon dioxide, carbon monoxide, methane, hydrogen) that will create a slightly oxidizing gas environment. Little is known from direct experiments on the reactivity of thir… more
Date: September 1, 2013
Creator: Contescu, Cristian I
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Analysis of the Experimental Gas-Cooled Reactor Fuel Assemblies

Description: The design of the Experimental Gas-Cooled Reactor fuel assemblies is described and a brief outline of the experimental heat transfer and fluid dynamic studies and mechanical testing is given, and he results of their application to the fuel element analysis are shown. The failure criteria are presented, the hot-channel factors are described, and the expected fission-gas pressure buildup within the elements is discussed.
Date: September 27, 1963
Creator: Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Effects in the EGCR Fuel

Description: From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date: June 1965
Creator: Baumann, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Next Generation Nuclear Plant - Insights Gained from the INEEL Point Design Studies

Description: This paper provides the results of an assessment of two possible versions of the Next Generation Nuclear Plant (NGNP), a prismatic fuel type helium gas-cooled reactor and a pebble-bed fuel helium gas reactor. Insights gained regarding the strengths and weaknesses of the two designs are also discussed. Both designs will meet the three basic requirements that have been set for the NGNP: a coolant outlet temperature of 1000 C, passive safety, and a total power output consistent with that expected … more
Date: August 1, 2004
Creator: MacDonald, Philip E.; Baxter, A. M.; Bayless, P. D.; Bolin, J. M.; Gougar, H. D.; Moore, R. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Interim Status Report on the Design of the Gas-Cooled Fast Reactor (GFR)

Description: Current research and development on the Gas-Cooled Fast Reactor (GFR) has focused on the design of safety systems that will remove the decay heat during accident conditions, ion irradiations of candidate ceramic materials, joining studies of oxide dispersion strengthened alloys; and within the Advanced Fuel Cycle Initiative (AFCI) the fabrication of carbide fuels and ceramic fuel matrix materials, development of non-halide precursor low density and high density ceramic coatings, and neutron irr… more
Date: January 1, 2005
Creator: Weaver, Kevan D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Next Generation Nuclear Plant

Description: The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for bu… more
Date: January 1, 2009
Creator: Petti, Dr. David A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Intermediate Heat Transport Loop Design Configurations for Hydrogen Production Using High Temperature Nuclear Reactors

Description: The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power … more
Date: November 1, 2005
Creator: Oh, Chang; Davis, Cliff; Barner, Rober & Pickard, Paul
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor

Description: The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 900 degrees C or operational fuel temperatures above 1250 degrees C. These concepts provide the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation and nuclear hydrogen generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperatures to support pro… more
Date: November 1, 2004
Creator: Chang, H. Oh; Davis, Cliff & Moore, Richard
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GRSAC Users Manual

Description: An interactive workstation-based simulation code (GRSAC) for studying postulated severe accidents in gas-cooled reactors has been developed to accommodate user-generated input with ''smart front-end'' checking. Code features includes on- and off-line plotting, on-line help and documentation, and an automated sensitivity study option. The code and its predecessors have been validated using comparisons with a variety of experimental data and similar codes. GRSAC model features include a three-dim… more
Date: February 1, 1999
Creator: Ball, S.J. & Nypaver, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Fast Reactor (GFR) Decay Heat Removal Concepts

Description: Current research and development on the Gas-Cooled Fast Reactor (GFR) has focused on the design of safety systems that will remove the decay heat during accident conditions, ion irradiations of candidate ceramic materials, joining studies of oxide dispersion strengthened alloys; and within the Advanced Fuel Cycle Initiative (AFCI) the fabrication of carbide fuels and ceramic fuel matrix materials, development of non-halide precursor low density and high density ceramic coatings, and neutron irr… more
Date: September 1, 2005
Creator: Weaver, K. D.; Cheng, L. Y.; Ludewig, H. & Jo, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Measurement of Flow Phenomena in a Lower Plenum Model of a Prismatic Gas-Cooled Reactor

Description: Mean-velocity-field and turbulence data are presented that measure turbulent flow phenomena in an approximately 1:7 scale model of a region of the lower plenum of a typical prismatic gas-cooled reactor (GCR) similar to a General Atomics Gas-Turbine-Modular Helium Reactor (GTMHR) design. The data were obtained in the Matched-Index-of-Refraction (MIR) facility at Idaho National Laboratory (INL) and are offered for assessing computational fluid dynamics (CFD) software. This experiment has been sel… more
Date: May 1, 2008
Creator: Hugh M. McIlroy, Jr.; McEligot, Donald M. & Pink, Robert J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Fast Reactor (GFR) FY04 Annual Report

Description: The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, … more
Date: September 1, 2004
Creator: Weaver, K. D.; Totemeier, T. C.; Clark, D. E.; Feldman, E. E.; Hoffman, E. A.; Vilim, R. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Addition of Noncondensable Gases into RELAP5-3D for Analysis of High Temperature Gas-Cooled Reactors

Description: Oxygen, carbon dioxide, and carbon monoxide have been added to the RELAP5-3D computer code as noncondensable gases to support analysis of high temperature gas-cooled reactors. Models of these gases are required to simulate the effects of air ingress on graphite oxidation following a loss-of-coolant accident. Correlations were developed for specific internal energy, thermal conductivity, and viscosity for each gas at temperatures up to 3000 K. The existing model for internal energy (a quadratic … more
Date: August 1, 2003
Creator: Davis, C. B. & Oh, C. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Initial Requirements for Gas-Cooled Fast Reactor (GFR) System Design, Performance, and Safety Analysis Models

Description: The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, … more
Date: August 1, 2004
Creator: Weaver, Kevan D. & Wei, Thomas Y. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Modular Pebble Bed Reactor Project, University Research Consortium Annual Report

Description: This project is developing a fundamental conceptual design for a gas-cooled, modular, pebble bed reactor. Key technology areas associated with this design are being investigated which intend to address issues concerning fuel performance, safety, core neutronics and proliferation resistance, economics and waste disposal. Research has been initiated in the following areas: · Improved fuel particle performance · Reactor physics · Economics · Proliferation resistance · Power conversion system model… more
Date: July 1, 2000
Creator: Petti, David Andrew
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report

Description: The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 9000C or operational fuel temperatures above 12500C. These concepts provide the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation and nuclear hydrogen generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperatures to support process heat applic… more
Date: September 1, 2005
Creator: Oh, Chang
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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