Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
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Showing 1 to 13 of 13 for “"Very-high-temperature Reactor"”.
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Air Ingress and Heat-Driven Flow Relaminarization in a Very High Temperature Reactor (VHTR)
<p>Very High Temperature Reactors (VHTRs) are one of six Generation IV reactors that have been proposed for DOE’s Next Generation Nuclear Plant. In addition to using gaseous coolants, VHTRs also display benefits of passive safety systems including intra-core natural circulation for heat removal in …
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Microstructural evolution and mechanical behavior in nickel based alloys for very high temperature reactor
Under the Gen IV advanced reactor development program, the Very High Temperature Reactor (VHTR) is the lead concept. Design and development steps are currently underway to construct a high-temperature reactor as the next generation nuclear plant (NGNP) at Idaho National Laboratory (INL). A major …
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Oxidation behavior of very high temperature reactor (VHTR) candidate materials: 316l stainless steel, Alloy 617, and Incoloy-800H
High temperature nuclear reactors require alloys to perform well at temperatures around 1000 to 1400 K. The oxidation behavior of three high temperature reactor candidate materials, 316 L stainless steel, alloy 617, and Incoloy 800-H under different conditions were investigated in the present work. …
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Analysis of U-Zr-C-O Quaternary System for Applications in Advanced ZRC Coated Triso Particles
… of ZrC for use in oxide TRISO particles for Very High Temperature Reactor (VHTR) conditions to prevent kernel overpressurization and kernel migration has been proposed by several researchers. Analysis is performed incorporating first-principles thermodynamics along with out-of-pile …
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The Effect of Coating Parameters On Advanced TRISO Fuels With Zirconium Carbide
… the conventional SiC TRISO coating system at very high temperature, not unlike the temperatures obtainable in the very high temperature reactor (VHTR) design. These problems include but are not limited to over pressurization of the kernel due to fission gas buildup as well as kernel migration, …
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Plenum-to-plenum heat transfer characteristics under natural circulation in a scaled-down prismatic modular reactor
<p>“Gas-cooled reactor (GCR) is being developed under the Next Generation Nuclear Plant Program (NGNP) in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, GCR seems to be a …
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Experimental study of natural convection heat transfer and gaseous dynamics from dual-channel circulation loop
… within a component or region of the prismatic very high-temperature reactor (VHTR) such as plenum-to-plenum heat transfer and gaseous dynamics during natural circulation. Natural circulation of the coolant is the leading capability for VHTR to transport the decay heat from the core to the …
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Structural integrity assessment of engineering components under cyclic loading at high temperature
… components and structures in operation at high temperature. Nuclear power plant industry is one of a good example, and they have planned to introduce the very high temperature reactor to increase efficiency. The high temperature operations may improve power productions but cause severe …
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Swirling jets for the mitigation of hot spots and thermal Sstratification in the VHTR lower plenum
The literature indicates that a prismatic-core very high temperature reactor can experience thermal stratification and hot spot issues in the lower plenum (LP). This research hypothesizes that the complex thermalhydraulic phenomena in the LP requires a sophisticated computational fluid dynamics …
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CFD Modeling and Simulation of Natural Circulation in Helium- Cooled Very High Temperature Reactors
… behavior of natural circulation in helium-cooled Very High Temperature Reactor (VHTR) systems, focusing on the performance and validation of passive safety features under Pressurized or Depressurized Loss of Forced Cooling (P-LOFC or D-LOFC) events. An experimental facility inspired by the General …
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Physics-Based 3D Multi-Directional Reloading Algorithm for Deep Burn HTR Prismatic Block Systems
… of Transuranic (TRU) nuclides in nuclear reactors. Due to favorable performance characteristics, multiple studies are focused on transmutation options using High Temperature Gas-cooled Reactors (HTGRs). Prismatic HTGRs allow for 3-Dimensional (3D) fuel shuffling and prior shuffling …
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An Effective Methodology for Thermal-Hydraulics Analysis of a VHTR Core and Fuel Elements
The Very High Temperature Reactor (VHTR) is a Generation-IV design in the conceptual pre-licensing phase for potential construction by 2030-2050. It is graphite moderated, helium cooled reactor that operates at an exit temperature of up to 1273 K, making it ideal for generating electricity at a …
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High temperature creep-fatigue behavior of alloy 617 and alloy 230
The Very High Temperature Reactor (VHTR) is one of the Gen-IV reactor design concepts which embody a common goal of providing safe, longer lasting, proliferation-resistant, and economically viable nuclear energy. One of the biggest challenges in the research and development of Gen-IV reactor …