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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 57 for “"fast reactors"”.
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Radial power flattening in sodium fast reactors
… a new design for a uranium startup sodium cooled fast reactor which was proposed at MIT, this thesis evaluated radial power flattening by varying the fuel volume fraction at a fixed U-235 enrichment of 18.5%. Of particular interest was how best to reduce the radial power peaking at the center of …
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Innovative design of uranium startup fast reactors
Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, …
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Analysis of severe reactivity excursions in fast reactors.
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1970. Ph.D.
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Development of thermodynamic cycles for sodium-cooled-fast reactors.
… 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 thermophysical, corrosion, and neutronic …
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In Core Fuel Management Studies of Large Fast Reactors
Made available in DSpace on 2014-12-11T17:26:06Z (GMT). No. of bitstreams: 1 7219938.pdf: 3339213 bytes, checksum: aaf2806d617fa53402a2c3513b799462 (MD5) Previous issue date: 1972
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Reactor physics design of supercritical CO₂-cooled fast reactors
Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO₂ (S-CO₂) as a Brayton cycle working fluid in a direct cycle is evaluated. By using S- CO₂ at turbine inlet conditions of 20 MPa and …
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Reactor protection system design alternatives for sodium fast reactors
… that can significantly challenge sodium-cooled fast reactors. The perceived potential consequences of a severe unprotected transient in a sodium-cooled fast reactor include an energetic core disruptive accident, vessel failure, and a large early release. These consequences can be avoided if …
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Reactivity Effects Due to Isotope Concentration Changes in Fast Reactors
Made available in DSpace on 2017-07-06T18:55:51Z (GMT). No. of bitstreams: 2 Peters_John_R_MS.pdf: 38930475 bytes, checksum: 3c882d1f1b96072afa93e6823067e570 (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1983
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Probabilistic transient analysis of fuel choices for sodium fast reactors
… framework to inform the design of Sodium Fast Reactors. NUREG-1860, more commonly known as the Technology Neutral Framework (TNF), is a risk-informed licensing process drafted by the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research. The TNF determines the …
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Optimization of actinide transmutation in innovative lead-cooled fast reactors
… investigates the potential of fertile free fast lead-cooled modular reactors as efficient incinerators of plutonium and minor actinides (MAs) for application to dedicated fuel cycles for transmutation. A methodology is developed that assesses the actinide incineration performance of several …
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Multigroup, Spatially Dependent Studies of Mild Excursions in Large Fast Reactors
Made available in DSpace on 2014-12-11T17:26:05Z (GMT). No. of bitstreams: 1 7121211.pdf: 4419876 bytes, checksum: 0f7b829cc1bb034c93001e952ce2ebfa (MD5) Previous issue date: 1971
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Design of compact intermediate heat exchangers for gas cooled fast reactors
… CO2 Brayton power cycle to a helium cooled fast reactor core. In particular, the wavy channel friction factor and the effective conduction thickness between channels were evaluated by simulations using state of the art software (FluentTm). To support the competitiveness of the PCHE, it was …
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Application of the technology neutral framework to sodium cooled fast reactors
Sodium cooled fast reactors (SFRs) are considered as a novel example to exercise the Technology Neutral Framework (TNF) proposed in NUREG- 1860. One reason for considering SFRs is that they have historically had a licensing problem due to postulated core disruptive accidents. Two SFR designs are …
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Development of Metallic Fuel Additives and Alloys for Sodium-cooled Fast Reactors
The major goal of the work is to develop effective additives for U-10Zr (wt.%) metallic fuel to mitigate the fuel-cladding chemical interactions (FCCIs) due to fission product lanthanides and to optimize the fuel phase mainly by lowering the gamma-onset temperature. The additives Sb, Mo, Nb, and Ti …
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Comparisons of Transport and Diffusion Theory Calculations of Performancecharacteristics for Large Fast Reactors
Made available in DSpace on 2014-12-11T17:26:01Z (GMT). No. of bitstreams: 1 7105217.pdf: 5163120 bytes, checksum: d6b149182da08b0eaafee8cb4aae9f1d (MD5) Previous issue date: 1970
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Evaluation of ethane as a power conversion system working fluid for fast reactors
… it appears that ethane might recombine much faster than it dissociates, which would be highly advantageous. Further research and experimentation is encouraged. Simple experiments should be sufficient to identify the behavior of ethane at high temperatures and pressures. Ethane was calculated …
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Applying risk informed methodologies to improve the economics of sodium-cooled fast reactors
… for nuclear waste management, the Sodium-Cooled Fast Reactor (SFR) is being developed. The main drawback has been its high capital and operating costs in comparison with traditional light water reactors. In order to compete, the SFR must be shown to be economically competitive. This study makes …
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Characterization of Uranium Carbide Microspheres In An Inert Zirconium Carbide Matrix For Gas Fast Reactors
… of an advanced nuclear fuel for Gas Fast reactors has been studied. Portions of a dispersion/composite fuel involving Uranium Carbide (UC) and Zirconium Carbide (ZrC) have been characterized and studied. Uranium carbide (UC) microspheres produced in the USC-Nuclear Materials …
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Tools for supercritical carbon dioxide cycle analysis and the cycle's applicability to sodium fast reactors
The Sodium-Cooled Fast Reactor (SFR) and the Supercritical Carbon Dioxide (S-C0₂) Recompression cycle are two technologies that have the potential to impact the power generation landscape of the future. In order for their implementation to be successful, they must compete economically with existing …
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Integrated fuel performance and thermal-hydraulic sub-channel models for analysis of sodium fast reactors
Sodium Fast Reactors (SFR) show promise as an effective way to produce clean 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 …
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