Coated particle fuel: Historical perspectives and current progress
暂无分享,去创建一个
[1] J. Hunn,et al. Determining the minimum required uranium carbide content for HTGR UCO fuel kernels , 2017 .
[2] John D. Hunn,et al. Detection and analysis of particles with failed SiC in AGR-1 fuel compacts , 2016 .
[3] B. Collin. AGR-2 Irradiation Test Final As-Run Report , 2014 .
[4] R. Bullock. Fission-product release during postirradiation annealing of several types of coated fuel particles , 1984 .
[5] M.S.T. Price,et al. FUEL ELEMENT FABRICATION FOR THE DRAGON REACTOR EXPERIMENT. , 1966 .
[6] Gregory K. Miller,et al. The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel , 2007 .
[7] G. Jellison,et al. Increase in pyrolytic carbon optical anisotropy and density during processing of coated particle fuel due to heat treatment , 2008 .
[8] Y. Katoh,et al. Microstructure and mechanical properties of heat-treated and neutron irradiated TRISO-ZrC coatings , 2015 .
[9] K. Notz,et al. Gel-sphere-pac fuel for thermal reactors: assessment of fabrication technology and irradiation performance , 1979 .
[10] M. A. Fütterer,et al. HTR-PM fuel pebble irradiation qualification in the high flux reactor in Petten , 2017 .
[11] Andrew C. Kadak,et al. The Status of the US High-Temperature Gas Reactors , 2016 .
[12] H. Nabielek,et al. High-Temperature Reactor Fuel Fission Product Release and Distribution at 1600 to 1800°C , 1991 .
[13] D. G. Martin,et al. RECENT DEVELOPMENTS OF COATINGS FOR GCFR AND HTGCR FUEL PARTICLES AND THEIR PERFORMANCE. , 1972 .
[14] Per F. Peterson,et al. The current status of fluoride salt cooled high temperature reactor (FHR) technology and its overlap with HIF target chamber concepts , 2014 .
[15] J. Hunn,et al. Fabrication and characterization of driver-fuel particles, designed-to-fail fuel particles, and fuel compacts for the US AGR-3/4 irradiation test , 2014 .
[16] E. Olivier,et al. Fission products silver, palladium, and cadmium identification in neutron-irradiated SiC TRISO particles using a Cs-Corrected HRTEM , 2016 .
[17] Karl Verfondern,et al. Major milestones of HTR development in Germany and still open research issues , 2018, Annals of Nuclear Energy.
[18] John Saurwein,et al. The DOE advanced gas reactor fuel development and qualification program , 2005 .
[19] P. Demkowicz. AGR-1 Post Irradiation Examination Final Report , 2015 .
[20] Chunhe Tang,et al. Fuel irradiation of the first batches produced for the Chinese HTR-10 , 2006 .
[21] M. Kissane,et al. Fission-product behaviour in irradiated TRISO-coated particles: Results of the HFR-EU1bis experiment and their interpretation , 2011 .
[22] Density functional theory metadynamics of silver, caesium and palladium diffusion at β-SiC grain boundaries , 2015 .
[23] J. O’Connell,et al. Ag transport in high temperature neutron irradiated 3C-SiC , 2014 .
[24] Kazuhiro Sawa,et al. Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup , 2003 .
[25] James L. Everett,et al. Peach bottom unit no. 1: A high performance helium cooled nuclear power plant , 1978 .
[26] S. Saito,et al. Design of high temperature Engineering Test Reactor (HTTR) , 1994 .
[27] M.S.T. Price,et al. The Dragon Project origins, achievements and legacies , 2012 .
[28] D. Kern,et al. Studies on the coating of fuel particles for the ‘dragon’ reactor experiment , 1967 .
[29] M. Kania,et al. Testing of HTR UO2 TRISO fuels in AVR and in material test reactors , 2013 .
[30] W. V. Goeddel. COATED-PARTICLE FUELS IN HIGH-TEMPERATURE REACTORS: A SUMMARY OF CURRENT APPLICATIONS. , 1967 .
[31] M. A. Fütterer,et al. Results of the HFR-EU1 fuel irradiation of INET and AVR pebbles in the HFR Petten , 2012 .
[32] Shigeaki Nakagawa,et al. Achievement of Reactor-Outlet Coolant Temperature of 950°C in HTTR , 2004 .
[33] Kurt A. Terrani,et al. Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics , 2018 .
[34] K. Iwamoto,et al. Fission product diffusion in ZrC coated fuel particles , 1979 .
[35] G. Hawkes,et al. The AGR-3/4 fission product transport irradiation experiment , 2018 .
[36] Kazuhiro Sawa,et al. Development of high temperature gas-cooled reactor (HTGR) fuel in Japan , 2011 .
[37] H. Nabielek,et al. Silver Release from Coated Particle Fuel , 1977 .
[38] H. Nabielek,et al. Fuel accident performance testing for small HTRs , 1990 .
[39] S. Jaye,et al. High-temperature gas-cooled reactor fuel and fuel cycles — their progress and promise☆ , 1968 .
[40] T. Tiegs. Fission product Pd-SiC interaction in irradiated coated-particle fuels , 1982 .
[41] K. Field,et al. Effect of exposure environment on surface decomposition of SiC-silver ion implantation diffusion couples , 2015 .
[42] H. Allelein,et al. Simulated accident testing of a fuel element from the HFR-EU1bis irradiation campaign , 2014 .
[43] Gregory K. Miller,et al. Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance , 2003 .
[44] J. Stempien,et al. Ceramography of irradiated TRISO fuel from the AGR-2 experiment , 2017 .
[45] W. J. Lackey,et al. Production of Spherical UO2‐UC2 for Nuclear Fuel Applications Using Thermochemical Principles , 1982 .
[46] Shusaku Shiozawa,et al. Research and Development of HTTR Coated Particle Fuel , 1991 .
[47] H. Nabielek,et al. Long time experience with the development of HTR fuel elements in Germany , 2002 .
[48] David A. Petti,et al. TRISO-Coated Particle Fuel Performance , 2012 .
[49] R. F. Turner,et al. HTGR fuel performance in the Peach Bottom Reactor , 1973 .
[50] H. Nabielek,et al. Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment , 2014 .
[51] Nobuyuki Suzuki,et al. Improvements in Quality of As-Manufactured Fuels for High-Temperature Gas-Cooled Reactors , 1997 .
[52] R. E. Bullock,et al. Performance of coated UO2 particles gettered with ZrC , 1983 .
[53] H. Ragoss,et al. Spherical fuel elements for advanced HTR manufacture and qualification by irradiation testing , 1990 .
[54] D. P. Harmon,et al. The Mechanical Design of TRISO-Coated Particle Fuels for the Large HTGR , 1972 .
[55] Y. Katoh,et al. Properties of Zirconium Carbide for Nuclear Fuel Applications , 2013, Comprehensive Nuclear Materials.
[56] C. L. Smith. SiC‐Fission Product Reactions in HTGR TRISO UC2 and UCxQy Fissile Fuel: II, Reactions Under Isothermal Conditions , 1979 .
[57] M. Wagner-Löffler. Amoeba behavior of UO/sub 2/ coated particle fuel , 1977 .
[58] Robert Noel Morris,et al. Estimation of maximum coated particle fuel compact packing fraction , 2007 .
[59] H. Nickel,et al. The behaviour of spherical HTR fuel elements under accident conditions , 1984 .
[60] J. Oxley,et al. CERAMIC-COATED-PARTICLE NUCLEAR FUELS , 1964 .
[61] Jeffrey J. Powers,et al. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview , 2017 .
[63] A. Naoumidis,et al. Silicon Carbide Corrosion in High-Temperature Gas-Cooled Reactor Fuel Particles , 1977 .
[64] H. Nabielek,et al. COATED PARTICLE FUEL FOR HIGH TEMPERATURE GAS COOLED REACTORS , 2007 .
[65] M. A. Fütterer,et al. Results of AVR fuel pebble irradiation at increased temperature and burn-up in the HFR Petten , 2008 .
[66] D. Morgan,et al. Ag diffusion in SiC high-energy grain boundaries: Kinetic Monte Carlo study with first-principle calculations , 2016, 1607.05253.
[67] R. Hunt,et al. The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process , 2010 .
[68] David A. Petti,et al. Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel , 2018 .
[69] H. Nabielek,et al. Carbon monoxide formation in UO2 kerneled HTR fuel particles containing oxygen getters , 1986 .
[70] Kazuhiro Sawa,et al. Research and development on HTGR fuel in the HTTR project , 2004 .
[71] D. P. Harmon,et al. Properties Influencing High-Temperature Gas-Cooled Reactor Coated Fuel Particle Performance , 1977 .
[72] W. V. Goeddel. DEVELOPMENT AND UTILIZATION OF PYROLYTIC-CARBON-COATED CARBIDE FUEL FOR THE HIGH-TEMPERATURE GAS-COOLED REACTOR , 1964 .
[73] Jeffrey Phillips,et al. Fabrication of uranium oxycarbide kernels and compacts for HTR fuel , 2012 .
[74] Chinthaka M. Silva,et al. Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form , 2015 .
[75] M. Taheri,et al. Transmission electron microscopy investigation of Ag diffusion mechanisms in β-SiC , 2015 .
[76] K. Verfondern,et al. Irradiation performance and modeling of HTR-10 coated fuel particles , 2006 .
[77] O. M. Stansfield. Evolution of HTGR coated particle fuel design , 1991 .
[78] R. L. Beatty,et al. Stoichiometric Effects on Performance of High-Temperature Gas-Cooled Reactor Fuels from the U-C-O System , 1977 .
[79] S. Blaine Grover,et al. Status of the NGNP fuel experiment AGR-2 irradiated in the advanced test reactor , 2014 .
[80] Kazuhiro Sawa,et al. Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors , 2000 .
[81] Timothy D. Burchell,et al. A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP) , 2008 .
[82] H. Nabielek,et al. The fuel element of the HTR-module, a prerequisite of an inherently safe reactor , 1988 .
[83] M. Kania,et al. Coated Particle Fuels for High‐Temperature Reactors , 2015 .
[84] Xiuzhu Zhou,et al. Current status and future development of coated fuel particles for high temperature gas-cooled reactors , 2011 .
[85] K. Ikawa,et al. Coating microspheres with zirconium carbide , 1972 .
[86] Grain boundary diffusion of Ag through polycrystalline SiC in TRISO fuel particles , 2015 .
[87] Shohei Ueta,et al. Design of core components , 2004 .
[88] Hans Huschka,et al. Fuel for pebble-bed HTRs , 1984 .