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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 21 for “"fuel element"”.
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Fuel element performance maps for nuclear reactor operational decisions.
Thesis. 1978. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
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The Measurement of Radial Power Distributions in a Triga Fuel Element During Reactor Excursions
Made available in DSpace on 2014-12-09T19:52:21Z (GMT). No. of bitstreams: 1 6801756.pdf: 4454948 bytes, checksum: 8cdc2842f2755df7bfb6d71a3b8f0cf5 (MD5) Previous issue date: 1967
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CFD in support of development and optimization of the MIT LEU fuel element design
… of lateral power distribution of the MITR LEU fuel design was analyzed using Computational Fluid Dynamics. Coupled conduction and convective heat transfer were modeled for uniform and non-uniform lateral power distributions. It was concluded that, due to conduction, the maximum heat flux ratio …
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The use of experiments on a single fuel element to determine the nuclear parameters of reactor lattices,
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1967.
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An Experimental Study of the Neutron Spectrum and the Radial Power Distribution in a Fuel Element in the Illinois Advanced Triga Reactor
Made available in DSpace on 2014-12-11T17:26:12Z (GMT). No. of bitstreams: 1 7514187.pdf: 4500287 bytes, checksum: f6f8bd8d7345e0023e6c87ce9f41f32d (MD5) Previous issue date: 1975
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LEU-HEU Mixed Core Conversion Thermal-hydraulic Analysis and Coolant System Upgrade Assessment for the MIT Research Reactor
… 93%-enriched U-235 highly-enriched uranium (HEU) fuel to the low enriched uranium (LEU, <20%-enriched U-235) fuel, as part of the global non-proliferation initiatives. A high-density, monolithic uraniummolybdenum (U-10Mo) fuel matrix is chosen. The fuel element design is changed from 15-plate …
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Consideration of fuel behaviour in AGR-like FHR reactor design
… of Molten Salt Reactor (MSR) that uses solid fuel separated from the molten coolant salt. Previous work showed that British Advance Gas-cooled Reactor (AGR) technology can be used to potentially reduce the time required to develop FHRs. Using such proven technology ensures that much of the …
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Impact assessment for the MIT Research Reactor low enrichment uranium fuel fabrication tolerances
… uranium (HEU) to low enriched uranium (LEU) fuel. A new type of high-density LEU fuel based on a monolithic U-10Mo alloy is being qualified to allow the conversion of all remaining U.S. high performance research reactors including the MITR. The purpose of this study is to understand the …
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Feasibility Assessment of Adopting the ADDER Computer Code for the MIT Research Reactor Fuel Management
… with highly enriched uranium (HEU) plate-type fuel. Fuel management calculations for this reactor are performed using MCODE, which allows for the coupling of a neutron transport code and a depletion code. As part of the low-enriched uranium (LEU) fuel conversion program, the Advanced …
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Estudo do processamento termomecânico de liga experimental de zircônio e seu efeito nas propriedades mecânicas e formação de hidretos
… of nuclear reactors, particularly in the fuel element, for their excellent properties of corrosion resistance, mechanical resistance, thermal conductivity and low neutron absorption. The interaction with hydrogen during the operation of the reactor leads to the formation of hydrides, …
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A Study Of Intermittent Convective Heating Effects On Fine Fuel Ignition
… convective heating on the ignition of fine fuels during wildland fire spread. In this study, a novel pulsed-gas line burner similar to a Rubens' tube, driven by acoustic oscillations, is used to re-create the pulsations observed in wildland fires in a controlled environment. After …
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Friction pressure drop measurements and flow distribution analysis for LEU conversion study of MIT Research Reactor
… in the United States that utilizes plate-type fuel elements with longitudinal fins to augment heat transfer. Recent studies on the conversion to low-enriched uranium (LEU) fuel at the MITR, together with the supporting thermal hydraulic analyses, propose different fuel element designs for …
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Investigation of the corrosion behaviour of U-Al material test reactor fuel elements in repository relevant solutions and characterisation of the secondary phases formed
… irradiated U-Al material test reactor fuel elements is the main requirement of final disposal. To clarify the behaviour under these conditions corrosion experiments with non-irradiated fuel elements and with aluminium as cladding material were performed. The results are used to explain …
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Nuclear reactor multi-physics simulations with coupled MCNP5 and STAR-CCM+
… The first demonstration model, a single fuel element surrounded by water, consists of 9,984 CFD cells and 7,489 neutronic cells. The second model is a 3 x 3 PWR lattice model, consisting of 89,856 CFD cells and 67,401 neutronic cells. Fission energy deposition (fission and prompt gamma …
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Thermal hydraulic limits analysis for the MIT Research Reactor low enrichment uranium core conversion using statistical propagation of parametric uncertainties
… uranium (HEU) to low enrichment uranium (LEU) fuel. In addition to the fuel element re-design from 15 to 18 plates per element, a reactor power upgraded from 6 MW to 7 MW is proposed in order to maintain the same reactor performance of the HEU core. Previous approaches in analyzing the impact …
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SERPENT Modeling of the Transient Reactor Test Facility and Comparison with Measured Experimental Data
… into accident tolerant light water reactor fuels. In addition to the need for accident tolerant fuels testing there is a rising demand for clean renewable energy and the design of many generation IV reactors to fill the role which will require testing of such reactors and their fuels. …
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Conceptual design of an annular-fueled superheat boiling water reactor
The conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is outlined. The proposed design, ASBWR, combines the boiler and superheater regions into one fuel assembly. This ensures good neutron moderation throughout the reactor core. A single fuel design is used in the core. …
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Development of a core design optimization tool and analysis in support of the planned LEU conversion of the MIT Research Reactor (MITR-II)
… weapons-grade uranium. In support of efficient fuel management analysis with the new LEU fuel, a core design optimization tool has been developed. Using a coarse model, the tool can quickly consider the large range of refueling options available, and identify a solution which minimizes power …
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An Effective Methodology for Thermal-Hydraulics Analysis of a VHTR Core and Fuel Elements
… flow in the interstitial gaps between the core fuel elements. This research, performed at the UNM-ISNPS, developed an effective thermal-hydraulics analyses methodology that markedly reduces the numerical meshing requirements and computational time. It couples the heliums 1-D convective flow and …
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Thermal-Hydraulic Analysis for the Proposed Upgrade of the Univeristy of Illinois Advanced TRIGA Reactor to 3 MW
Made available in DSpace on 2017-07-06T18:48:15Z (GMT). No. of bitstreams: 3 Golchert_Lucia_MS.pdf: 56434124 bytes, checksum: 34880e25e1902be6c97ff7f2373b2345 (MD5) Golchert_Lucia_MS_ABS.pdf: 591212 bytes, checksum: b4b3dbdb931bc4400e29804f1b1cd526 (MD5) license.txt: 4813 bytes, checksum: …
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