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 16 of 16 for “"neutron fluxes"”.
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Transmutation rates in the annulus gas of pressure tube water reactors
… Since fuel bundles are continuously under high neutron fluxes, annulus gas nuclides undergo different nuclear transformations generating new composition of the gas that might have different physical properties which are undesirable for the annulus system. In addition, gas nuclides become …
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A thermal-hydraulic analysis of the cooling system for the 500 KW Virginia Polytechnic Institute and State University reactor
… research reactor, it is necessary to enhance the neutron fluxes available in the experimental facilities. One method of attaining this objective is to increase the power level of the reactor. The VPI&SU 100 KW research reactor has been studied to investigate the feasibility of operation of 500 KW. …
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PREDICTING ACTIVATION OF EXPERIMENTS INSIDE THE ANNULAR CORE RESEARCH REACTOR
… is achieved by using MCNP to model the neutron fluxes in the reactors central cavity where experiments are conducted using one of the four possible neutron spectra available in the ACRR. The desired neutron spectrum, experiment material composition, and reactor power level are then input …
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A Bf3 Fast Neutron Dosimeter (Long Counter)
A BF3 fast neutron dosimeter or long counter is constructed and calibrated for use with the Cockcroft-Walton accelerator and UTR-IO reactor at Virginia Polytechnic Institute. The counter consists of a paraffin cylinder 8 inches in diameter, having a BF3 proportional detector on the axis and a set …
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An application of Chebyshev polynomials to the solution of a two-dimensional elliptic boundary-value problem
… to approximate solutions to the two-dimensional neutron diffusion equation. The two-dimensional two-group neutron diffusion equations are solved by expanding neutron fluxes in a finite series of Chebyshev polynomials over large regions of a fission reactor. All the equations for the expansion …
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Production and separation of medically relevant terbium-161 for radiopharmaceutical applications and recycling of target materials
… and purification of 161Tb using high-flux neutron irradiation and multi-step chromatographic separation. Enriched [160Gd]Gd(NO3)3 and [160Gd]Gd2O3 targets (98.2-99.96% isotopic enrichment) were irradiated at the University of Missouri Research Reactor (MURR) at thermal neutron fluxes of …
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Investigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactor
… damage and nuclear heating resulting from high neutron fluxes. The use of a sub-meter inner shield creates potential for the design of a proof of principle magnetic fusion device, sacrificing the central component materials for a demonstration of temporary fusion power production. The nuclear …
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Optimal initial fuel distribution in a thermal reactor for maximum energy production
… program, from which the spatially-averaged neutron fluxes and control poison cross sections are obtained. A uniform initial fuel distribution was chosen as a benchmark and the results for several different fuel configurations were analyzed. Two different initial control poison distributions …
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Development of a low enrichment uranium core for the MIT reactor
… in an attempt to eliminate the reductions in neutron flux available to experiments due to the conversion to LEU fuel, as well as increasing the flexibility for meeting the needs of in-core experiments. The optimum configuration of fuel plates was made by varying the plate number and …
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Diagnostics of solar flare energetic particles: neglected hard X-ray processes and neutron astronomy in the inner heliosphere
… we also have an interest in studying solar neutrons. To this end, this thesis presents our work done with new-age neutron detectors developed by our colleagues at the University of New Hampshire. Using laboratory and simulated data from the detector to produce its response matrix, we then …
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Developing fuel management capabilities based on coupled Monte Carlo depletion in support of the MIT Research Reactor (MITR) conversion
… using monolithic U-Mo LEU fuel while achieving neutron fluxes close to that of an HEU core. However, to date, detailed studies on fuel management and burnup while using LEU fuel have not been performed. In this work, a code package is developed for performing detailed fuel management studies at …
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Neutron production in a spherical phantom aboard the international space station
… that pose specific health risks, are created. Neutrons are one important component of this mixed radiation field due to their high LET. Therefore, the assessment of the neutron dose contribution has become an important part of the safety and monitoring program onboard the ISS. The need to …
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Part I. Cytochrome c oxidase active-site modeling: Synthesis and characterization of new unsymmetrical tris(imidazole- and pyridine-appended) picket-fence porphyrins and their metal complexes. Part II. Toward fullerene-based radiopharmaceuticals: High-yield neutron activation of endohedral holmium-165 metallofullerenes
… and empty C 60 were then bombarded with neutrons under differing flux conditions to understand the various modes of compound degradation and to maximize yields of activated 166 Ho x @C 82/84 [ 165 Ho(n,γ) 166 No]. C 60 survived irradiation to a fairly high extent (>80%) at total neutron …
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Mechanical characterization of alloy 709 stainless steel after high temperature aging for application in advanced reactors
… operate at higher temperatures and have higher neutron fluxes and thus require the use of novel materials. These materials will need to withstand an extreme environment, including corrosion from liquid sodium. Alloy 709 is a derivative of NF709, a high strength austenitic stainless steel …
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Advancement of liquid lithium plasma-facing components for next-generation fusion devices
… is handling the large heat, plasma and neutron fluxes exhausted from the core plasma. Current tokamak design points assume a steady state heat flux of 10MW/m2 increasing to values >1GW/m2 in transient events and particle fluxes > 1 × 1023m−2s−1. Flowing liquid lithium Plasma Facing …
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Finite Element Analysis of a Nuclear Pumped Heat Pipe with Heat Transfer to a Compressible Fluid
Made available in DSpace on 2017-07-06T18:59:39Z (GMT). No. of bitstreams: 3 Zediker_Mark_S_MS.pdf: 49651468 bytes, checksum: 6eb32f068e800580bfc0c563a07bdd23 (MD5) Zediker_Mark_S_MS_ABS.pdf: 474329 bytes, checksum: 51034f9078c08c3e89ce3b4d2735bd43 (MD5) license.txt: 4813 bytes, checksum: …