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 17 of 17 for “"Breeder reactor"”.
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Ssessment methodology for proliferation resistant fast breeder reactor
… perceived proliferation risks, current US fast reactor designs have avoided the use of uranium blankets. While reducing the amount of plutonium produced, this omission also restrains the reactor design space and has several disadvantages over blanketed cores. This study investigated many blanket …
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Thermal Performance Study of Liquid Metal Fast Breeder Reactor Insulations
Three types of metallic thermal insulations were investigated analytically and experimentally. These were multilayer reflective plates, multilayer honeycomb composite and multilayer screen insulation. Each of these insulations was subjected to evacuated and non-evacuated conditions where thermal …
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The economics of fuel depletion in fast breeder reactor blankets.
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Ph.D.
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Evaluation of a gas-cooled fast breeder reactor for ship propulsion.
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1972. Nucl.E.
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Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor
Current interest in advanced nuclear energy and MSR concepts has enhanced demand in building the tools to analyze these systems. This thesis introduces a Python script, SaltProc, which simulates MSR online reprocessing by modeling the changing isotopic composition of an irradiated fuel salt. …
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Analysis of and comparison between reprocessing methods in the molten salt breeder reactor
Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2024-03-01 without embargo terms
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An accident probability analysis and design evaluation of the gas-cooled fast breeder reactor demonstration plant
Thesis. 1976. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
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Correlations for the Rise Rate of the Hot-Cold Interface in a Liquid Metal Fast Breeder Reactor
Made available in DSpace on 2017-07-06T18:48:23Z (GMT). No. of bitstreams: 3 Harrell_Jefferson_A_MS.pdf: 31713450 bytes, checksum: 27c1e5b3af89b1908da4ebb03dc8524b (MD5) Harrell_Jefferson_A_MS_ABS.pdf: 355491 bytes, checksum: 9ff558e4b686af937bff33dfdff162ec (MD5) license.txt: 4813 bytes, checksum: …
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A Simple Computational Model for the Prediction of Fuel Pin Failure During A Transient-Overpower Accident
… (TOP) accident in a liquid metal fast breeder reactor. The principal failure mechanisms of fuel-cladding differential thermal expansion and fission-gas pressurization are accounted for.
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Conversion ratios for plutonium recycle in light water reactors: breeding potential in D₂O-H₂O cooled reactors
… A preliminary design for a D₂O-H₂O cooled breeder reactor is presented and the breeding characteristics of such a core are examined.
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Thorium oxide dissolution kinetics for hydroxide and carbonate complexation
… to better understand the behavior of thorium breeder reactor fuel in a repository environment, the behavior of thorium oxide was investigated. The kinetics of crystalline thorium oxide dissolution were studied under argon and argon/10% CO2 over a broad pH range in 0.1 M ionic strength NaC1O4 …
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Nuclear fission and social fusion: the impact of the Dounreay Experimental Research Establishment on Caithness, 1953-1966
… Caithness was now at the heart of Britain’s fast breeder reactor development: in assessing this, this thesis alters the understanding of what could be achieved in an area considered ‘remote’ in the mid-twentieth century. It prioritises the local consequences of a vast project which is commonly …
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Partial singular integro-differential equations models for dryout in boilers
… in steam generating pipes of a liquid metal fast breeder reactor is proposed. The model is based on thin-layer lubrication theory and thin aerofoil theory. The exchange of mass between the vapour core and the liquid film due to evaporation of the liquid film is accounted for in the model. The mass …
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Development of thermodynamic cycles for sodium-cooled-fast reactors.
… level of 40-62%. As there are six GEN-IV nuclear-reactor concepts and the performance of these reactors-concepts depends on their design, it is reasonable to start with all GEN-IV reactor concepts and investigate the coolants and their characteristics in these concepts. For this objective, main …
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An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle
… to uranium. The pressure tube heavy water reactor (PT-HWR) has for decades been considered capable of achieving net breeding on the thorium fuel cycle, but this capability has not been conclusively demonstrated. The goal of this work was to perform reactor physics modelling of the …
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Fuel processing simulation tool for liquid-fueled nuclear reactors
Nuclear reactors with liquid fuel offer multiple advantages over their solid-fueled siblings: improved inherent safety, fuel utilization, thermal efficiency, online reprocessing, and potential for nuclear fuel cycle closure. To advance this promising reactor design, researchers need a simulation …