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 22 for “"fuel pin"”.
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Thermomechanical analysis of innovative nuclear fuel pin designs
… reactor is to change the solid cylindrical fuel to Internally and Externally Cooled (I&EC) annular fuel, and adjust the flow and the core inlet coolant temperature. The switch to annular fuel allows for a 20% increase in core power density without changing the assembly size or the control …
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Wire wrapped fuel pin hexagonal arrays for PWR service
This work contributes to the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). Core design is accomplished for both hydride and oxide-fueled cores over a range of geometries via …
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A Simple Computational Model for the Prediction of Fuel Pin Failure During A Transient-Overpower Accident
A fuel pin failure model is developed and incorporated into a fast-running computer program. The model is designed to predict irradiated fuel-pin cladding rupture during a hypothetical transient-overpower (TOP) accident in a liquid metal fast breeder reactor. The principal failure mechanisms of …
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A study of solute transport of radiolysis products in crud and its effects on crud growth on PWR fuel pin
… the behavior of the porous crud growth on PWR fuel pins. This model employs a system of coupled mass transport and chemical interactions as the source term, which make the problem non-linear. A Monte Carlo technique is adopted to simulate the behavior of the different species. The direct …
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Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores.
Thesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977
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Integrated fuel performance and thermal-hydraulic sub-channel models for analysis of sodium fast reactors
… safe nuclear power while properly managing the fuel cycle. Accurate computer modeling is an important step in the design and eventual licensing of SFRs. The objective of this work was to couple a model for metal fuel performance to a sub-channel analysis code to more precisely predict critical …
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Optimization of a seed and blanket thorium-uranium fuel cycle for pressurized water reactors
… which employs a thorium/uranium once through fuel cycle, is optimized for good economics, wide safety margins, minimal waste burden and high proliferation resistance. The focus is on the Whole Assembly Seed and Blanket (WASB) concept, in which the individual seed and blanket regions each …
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Modeling and design of reload LWR cores for an ultra-long operating cycle
… research was to use state-of-the-art nuclear and fuel performance design packages to develop extended cycle cores for existing Light Water Reactor (LWR) designs which respect current fuel burnup limits while considering the full range of practical design and economic considerations. The driving …
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Three dimensional heterogeneous finite element method for static multi-group neutron diffusion
… neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; one which becomes more difficult with increased core heterogeneity. A three-dimensional Heterogeneous Finite Element Method (HFEM) is …
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High pressure counterflow CHF.
… An internally heated annulus was used to model a fuel pin in a channel. Only low flowrates were examined. The flow regime was always bubbly or slug, with the liquid primarily on the walls. It was found that critical heat flux of about .9 of the pool boiling value can be expected for up to 20% …
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Modelling of thermo-mechanical and irradiation behavior of metallic and oxide fuels for sodium fast reactors
… the irradiation behavior of metal and oxide fuels in sodium cooled fast reactors is developed. Modeling capability was enhanced by adopting a non-empirical mechanistic approach to the extent possible, so that to increase the ability to extrapolate the existing database with a reasonable …
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Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion
… NTP performance were considered by improving the fuel margin to melting point. A thorium-dioxide stabilized, high-assay low enriched uranium (HALEU) tungsten-uranium dioxide (W-UO2) CERMET fueled nuclear thermal propulsion (NTP) concept was produced based on the Space Capable Cryogenic Thermal …
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Advanced design concepts for PWR and BWR high-performance annular fuel assemblies
… through the development of advanced annular fuel designs with both internal and external cooling which can achieve higher power densities and hence, higher electricity output from the same basic reactor vessel and containment. Therefore the objectives of this project are to determine the …
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An evolutionary fuel assembly design for high power density BWRs
An evolutionary BWR fuel assembly design was studied as a means to increase the power density of current and future BWR cores. The new assembly concept is based on replacing four traditional assemblies and large water gap regions with a single large assembly. The traditional BWR cylindrical …
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Investigation of pellet-clad interaction during load-follow operation in a pressurized water reactor using VERA-CS
… study on the effect load-follow operation has on fuel failure risk in a PWR. PWR1, a commercial reactor that performed load-follow power maneuvers in cycle 21, was modeled using VERA-CS. The effects of a jump-in approach, starting depletion in cycle 17 as compared to cycle 1, were shown to be …
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Investigation of pressure-tube and calandria-tube deformation following a single channel blockage event in ACR-700
… resulting in rapid coolant boil-off and fuel overheating. Melting of the Zircaloy (Zry) components of the fuel bundle (cladding, end plates and end caps) can occur, with relocation of some molten material to the bottom of the PT. The hot spot caused by the molten Zry/PT interaction may …
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Uncertainty quantification for safety verification applications in nuclear power plants
… was obtained for output pressure and 0.048% for fuel pin temperature in the RD-14 test case. These results are expected to be useful for providing insight into safety margins related to safety analysis and verification.
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Carbon deposition on transition metal- and uranium-oxides
… present. Carbon deposition on boiler and fuel pin heat transfer surfaces affects a reactor's efficiency and may necessitate downrating to maintain safety margins. This is believed to arise from decomposition of some of the coolant gas constituents. Deposition minimisation, while …
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Neutronic Characteristics of Using Zirconium Diboride and Gadolinium in a Westinghouse 17 X 17 Fuel Assembly
… In order to achieve this, variations in fuel composition, fuel pin arrangement, and burnable absorber distribution have been proposed. Burnable absorbers are materials that absorb the neutrons that cause a nuclear fission reaction and are consumed (burned) in the process. With a higher …
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Analysis and optimization of a new accident tolerant fuel called fuel-in-fibers
… highlighted the weakness of the current nuclear fuel and motivated R&D of accident tolerant fuels. Accident tolerant fuels (ATF) are fuels that can tolerate loss of active cooling in the core of light water reactors (LWRs) for a considerably longer period of time while maintaining or improving …
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