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 70 for “"Fast Reactor"”.
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Space-Time Neutronics Applied to Fast Reactor Disassembly Calculations
Made available in DSpace on 2014-12-14T06:25:58Z (GMT). No. of bitstreams: 1 7616216.pdf: 4296525 bytes, checksum: 2ee10e2ad4bf78a3664513e4ac49ad7f (MD5) Previous issue date: 1976
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Proton-recoil neutron spectrometry in a fast reactor blanket.
Thesis: M.S., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1973
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Experimental verification of breeding performance of fast reactor blankets.
Thesis: Nuc. E., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1976
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An evaluation of the breed/burn fast reactor concept
Thesis (Sc.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980.
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A General Formulation of Neutron Noise for Fast Reactor Systems
… analyze zero-power neutron noise experiments in fast reactor systems. A generalized dispersion equation is combined with theoretical expressions for the experimentally measured power spectral density and variance-to-mean ratio which makes it possible to express these quantities in terms of a …
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Stability analysis of a natural circulation lead-cooled fast reactor
… analysis of a natural circulation lead cooled fast reactor design. The stability concerns arise from the fact that natural circulation operation makes the system susceptible to flow instabilities similar to those observed in boiling water reactors. In order to capture the regional effects, …
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Polonium extraction techniques for a lead-bismuth cooled fast reactor
The construction of a next generation fast nuclear reactor using liquid lead-bismuth as a coolant demands the design of applied technology to remove 210Po from the neutron activated lead-bismuth eutectic. Experiments were performed to determine the kinetics of polonium hydride and lead-polonide …
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Static corrosion of candidate alloys for the lead-bismuth fast reactor
… for use in Lead-bismuth Eutectic (LBE) cooled fast nuclear reactors. The two alloys examined were T91 and Fe-12Cr-2Si. An experimental study was performed to analyze the static corrosion on the two alloys. For the experiment, the polished samples of the two alloys were heated in LBE for 166 …
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Optimized core design of a supercritical carbon dioxide-cooled fast reactor
… renewed interest in nuclear 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 …
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Fluence-limited burnup as a function of fast reactor core parameters
The limiting factor in current designs for fast reactors is not only the reactivity, but also the maximum permissible fast-neutron fluence in the cladding, especially for reduced uranium enrichment cores using high-albedo MgO reflectors. The intent of this thesis was to determine the best design …
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Investigation of mechanical behavior of Alloy 709 for advanced fast reactor applications
The advent of next-generation nuclear reactor systems brings with it a multitude of material challenges. The structural materials to be used for these reactors will be exposed to more extreme conditions of radiation, stress, and temperature than those of prior generations. The development and …
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Implementation of vented fuel assemblies in the supercritical CO₂-cooled fast reactor
… in the reference design of the gas-cooled fast reactor under study as 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 …
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Thermal-hydraulic analysis of innovative fuel configurations for the sodium fast reactor
The sodium fast reactor (SFR) is currently being reconsidered as an instrument for actinide management throughout the world, thanks in part to international programs such as the Generation-IV and especially the Global Nuclear Energy Partnership (GNEP). The success of these programs, in particular …
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Hydrogen production using a supercritical CO₂-cooled fast reactor and steam electrolysis
… (HTSE) coupled with an advanced gas-cooled fast reactor (GFR) utilizing supercritical carbon dioxide (S-CO₂) as the coolant. The reasons for selecting this particular reactor include fast reactor uranium resource utilization benefits, lower reactor outlet temperatures than helium-cooled …
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Core design and reactor physics of a breed and burn gas-cooled fast reactor
… has focused on the design of a Gas-cooled Fast Reactor (GFR) operating in a Breed and Burnm (B&B) fuel cycle mode. B&B refers to a once-through fuel cycle where low enriched uranium (less than 5 w/o 235U in U) subcritical assemblies are loaded into the core in equilibrium, yet in-situ …
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Thermal hydraulic design of a 2400 MW t̳h̳ direct supercritical CO₂-cooled fast reactor
The gas cooled fast reactor (GFR) has received new attention as one of the basic concepts selected by the Generation-IV International Forum (GIF) for further investigation. Currently, the reference GFR is a helium-cooled direct cycle plant with core outlet temperatures in the 850"C to 10000C range. …
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The Philosopher's Plutonium Stone: the Dounreay Fast reactor and the fall of Britain's Atomic Empire
This thesis examines the Dounreay fast reactor project which became central to the survival of an indigenous nuclear engineering design and construction industry in the UK. Its focus is on the original reactor – DFR – which was given the go-ahead in 1953 and shut down in 1977, based on the premise …
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The Effect of Fuel Diameter on The Doppler Temperature Coefficient of Reactivity in Fast Reactor Systems
Made available in DSpace on 2014-12-09T19:52:21Z (GMT). No. of bitstreams: 1 6711884.pdf: 3731951 bytes, checksum: e3c2ac834c37ce5c582f3ade7c0e15c2 (MD5) Previous issue date: 1967
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