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 20 of 26 for “"Gen IV"”.
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The Deposition Characteristics of Zrc On Uo2 Kernels Produced For Advanced Triso Fuels In Gen-Iv Reactors
… the ability for using the process heat for hydrogen production and other commercial uses. However, the limits of operation of VHTRs are currently constrained by the ability of the tri-structural isotropic fuel (TRISO) to maintain its structural integrity under irradiation at temperatures of …
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Development of thermodynamic cycles for sodium-cooled-fast reactors.
Currently, one engineering challenge is designing Generation IV (GEN-IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies compared to current NPPs, and to match, or at least to be close to, the thermal efficiencies reached by fossil-fired power plants, which are currently …
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OXIDATION OF SILICON CARBIDE AND GRAPHITE FOR HIGH TEMPERATURE GAS-COOLED REACTOR APPLICATIONS
… as it pertains to accident scenarios in Gen IV thermal spectrum high temperature gas cooled nuclear reactors. It is imperative to understand the oxidation behavior of such materials to predict their response to off-normal environments and certify their accident tolerance to implement Gen …
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Implementation of vented fuel assemblies in the supercritical CO₂-cooled fast reactor
… part of the larger research effort at MIT under Gen-IV NERI Project No. 05-044, "Optimized Competitive Supercritical-CO₂ Cycle GFR for Gen-IV Service." The focus of this work is on selection and optimization of a fuel assembly configuration best suited for venting, assessment of the radionuclide …
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Reactor physics design of supercritical CO₂-cooled fast reactors
Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO₂ (S-CO₂) as a Brayton cycle working fluid in a direct cycle is evaluated. By using S- CO₂ at turbine inlet conditions of 20 MPa and …
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Development and characterization of nanostructured steels and high entropy alloys for nuclear applications
… (LWRs) and realize the development of advanced Gen IV nuclear reactors new materials must be developed which can withstand such an environment. This thesis involves two approaches to solving this materials problem: advanced manufacturing of current commercial alloys using severe plastic …
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Mean-Field Parameter Study of Radiation-Induced Segregation in a Binary Metal Alloy
… pursuit of advanced materials for deployment in Generation IV (Gen-IV) nuclear reactor designs. A mean-field study is conducted on a body-centered cubic (BCC) A-B binary metal alloy system. The performance of the simulated metal system is measured by assessing the degree of segregation that …
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High temperature creep-fatigue behavior of alloy 617 and alloy 230
… 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 systems is …
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Microstructural evolution of zirconium carbide (ZrCₓ) ceramics under irradiation conditions
<p>A comprehensive understanding of the microstructural evolution of Zirconium Carbide (ZrC<sub>2</sub>) ceramics under irradiation conditions is required for their successful implementation in advanced Gen-IV gas-cooled nuclear reactors. The research presented in this dissertation focusses on …
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Development of Modeling Techniques for A Generation IV Gas Fast Reactor
… These new reactors have come to be known as the Generation IV (Gen IV) class of nuclear reactors. Similarly to the other designs, the Gas Fast Reactor (GFR) has many advantages, such as electricity production at high efficiency, hydrogen production, minor actinide burning capabilities, etc. …
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The relationship between mechanical properties and microstructure of HT9 steel
Next-generation advanced reactor system designs present new challenges for material design and selection. The structural materials selected for these reactors will need to withstand higher operation temperatures, more neutron irradiation (greater flux), and corrosion from liquid metal coolants. …
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Optimized core design of a supercritical carbon dioxide-cooled fast reactor
… power, Gas-cooled Fast Reactors (GFRs) have received increasing attention in the past decade. Motivated by the goals of the Generation-IV International Forum (GIF), a GFR cooled by supercritical carbon dioxide (S-CO2), fueled with Light Water Reactor spent fuel transuranics, and directly coupled …
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Scaling siting criteria and identifying alternative licensing pathways for micro-reactors within the existing regulatory framework
Micro-reactors are a relatively recent subset of Gen IV reactors currently being developed, and due to their design features (i.e., no refueling onsite, easily transported, and mass produced), micro-reactors have the potential to tap into broader markets never accessed before by the nuclear sector …
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Analysis of required supporting systems for the supercritical CO₂ power conversion system
… additional benefit of the S-CO₂ system is its universal applicability as an indirect secondary Power Conversion System (PCS) coupled to most GEN-IV concept reactors, as well as fusion reactors. The United States DOE's GNEP is now focusing on the liquid Na cooled primary as an alternative to …
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Innovative design of uranium startup fast reactors
… Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, …
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Hydrogen and helium effects on reduced activation Fe-Cr ferrite-martensite and ODS steels
Significant amounts of hydrogen and helium are generated in the structural materials of the nuclear reactor systems by the interaction of the alloying elements with both fast and thermal neutrons. Hydrogen can also be effectively absorbed by other environmental processes. Helium and hydrogen …
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Developing 1-D heat transfer correlations for supercritical water and carbon dioxide in vertical tubes
… part of the energy mix since it offers a relatively clean, safe and reliable source of electrical energy. However, opportunities for building new generation nuclear systems will depend on their economic and safety attractiveness as well as their flexibility in design to adapt in different …
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Reduction of Solid Uranium Dioxide in Calcium Salts
… without nuclear energy. Another sign that the Generation IV International Forum (Kelly, Gen IV International Forum: A decade of progress through international cooperation, 2014) has pointed out is to utilize uranium resources to the maximum and recycle spent nuclear fuel through burn-up in the …
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Small modular reactor technology for industrial heat and power: selection techniques and implementation strategies for real-world use cases using systems-based approaches.
… in several countries around the world, from Gen-III+ light water SMRs, to Gen-IV SMRs and micro-reactors. All at various stages of development, from an early conceptual phase to operational deployment and commercialization. These SMRs are also being developed in multiple configurations, being …
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Exposure and Characterization of Candidate Materials for Use in Supercritical Water Reactors
… medium between a power source and the steam generating system lead to an increase in thermodynamic efficiency. Supercritical water systems have already been employed in fossil fuel power generation, and a proposed Gen IV nuclear reactor is designed to do the same which would result in an …
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