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Showing 1 to 20 of 32 for “"low-enriched"”.
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Nuclear Electric Propulsion with Low Enriched Uranium
… politically problematic fuel choice of highly enriched uranium (HEU). Using low enriched uranium (LEU, 20% U-235 by mass) avoids many of the security costs and public perception issues associated with HEU but has implications for the power system design. The core will require more fuel and/or a …
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Thermal-hydraulic optimization for high production of low-enriched uranium based molybdenum-99
… motivate the current reactors to stop using high-enriched uranium, the University of Missouri Research Reactor (MURR) has begun to produce molybdenum-99 using low-enriched uranium. The fission of uranium-235, for which one of the products is molybdenum-99, generates approximately 2 kW of heat per …
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Investigation of the impacts of deploying reactors fueled by high-assay low enriched uranium
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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Design Options to Address Submersion Criticality for Low-Enriched Uranium Nuclear Thermal Propulsion Rocket
Missions to Mars with eventual establishment of a Mars base/colony will require a versatile and consistent transportation method between Earth and Mars. Nuclear thermal propulsion (NTP) is well suited to be the main propulsion mechanism for interspace travel due to its high specific impulse. In …
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Thermal-mechanical analysis of targets for high volume production of molybdenum-99 using low-enriched uranium
… located in foreign countries and use highly enriched uranium (HEU). The University of Missouri Research Reactor (MURR) is exploring the feasibility of high volume molybdenum-99 production at its facility. Current molybdenum-99 production uses HEU in a powder dispersion target. The powder …
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Modelling of Graphite Elements and Low Enriched Fuel Assemblies for a High Temperature Gas-Cooled Reactor
… the channels that guide the helium coolant flow and contain the fuel compacts in the HC-HTGR. Given the low tensile strength of graphite, FEA analysis is required for predicting stresses within these components. The stresses are evaluated using the ASME code for graphite components in nuclear …
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Estimate of radiation release from MIT reactor with low enriched uranium (LEU) core during maximum hypothetical accident
… is planning on converting from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) for fuel. A component of the conversion analysis includes calculating the maximum hypothetical accident (MHA) dose implications for the two types of fuel. In this work, the dose levels at the site …
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Examination of the conversion of the U.S. submarine fleet from highly enriched uranium to low enriched uranium
… propulsion are currently fueled by highly enriched uranium (HEU), but HEU brings administrative and political challenges. This issue has been studied by the Navy before, and promising new fuel technology developments, combined with new motivations, warrant a fresh look at low enriched …
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Examination of the proposed conversion of the U.S. Navy nuclear fleet from highly enriched Uranium to low enriched Uranium
… of Nuclear Weapons creates a loophole that allows a non-nuclear-weapon country to avoid international safeguards governing fissile materials if it claims that the materials will be used for naval nuclear propulsion purposes. The United States ability to negotiate a closing of this loophole is …
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Validation of the use of low enriched uranium as a replacement for highly enriched uranium in US submarine reactors
The US Navy has long used highly enriched uranium (HEU) in naval reactors for a variety of technical reasons. In a series of studies, the Department of Naval Reactors determined that switching to low enriched uranium (LEU) was impossible using current fuel designs, but may be possible with a …
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Neutronic Performance and Thermal Hydraulic Analysis of the MIT Reactor Fission Converter Experimental Facility Using High-Density U-10Mo Low-Enriched Uranium Fuel Elements
… will remain subcritical (k _eff < 0.9) and low power (≤200 kW) under a wide range of performance conditions, including with both types of fuel and a variety of materials on the target-side of the FC tank. The HEU-fueled FC is expected to require no changes to the limiting safety system …
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Design of a low enrichment, enhanced fast flux core for the Massachusetts Institute of Technology Research Reactor
… for a new core to end the need for highly enriched uranium and operate the reactor with uranium enrichments under 20%. This study explores the use of the central region in the newly proposed MIT reactor core to boost the production of fast neutrons, thus making the new core more beneficial …
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Impact assessment for the MIT Research Reactor low enrichment uranium fuel fabrication tolerances
… (MITR) is planning to convert from highly enriched 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. …
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Core design and reactor physics of a breed and burn gas-cooled fast reactor
… 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 plutonium breeding carries the fuel through a discharge burnup on the order of 150 MWD/kgHM. The B&B fuel cycle meets the …
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Friction pressure drop measurements and flow distribution analysis for LEU conversion study of MIT Research Reactor
… 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 optimization of thermal hydraulic performance of the LEU core. Since proposed fuel design has a smaller …
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Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion
… point. A thorium-dioxide stabilized, high-assay low enriched uranium (HALEU) tungsten-uranium dioxide (W-UO2) CERMET fueled nuclear thermal propulsion (NTP) concept was produced based on the Space Capable Cryogenic Thermal Engine (SCCTE) reactor1. Axial fuel thoria fraction adjustments to improve …
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LEU+ Fuel Cycle Investigation of the BWRX-300 Design Using Neutronic and Two-Phase Thermal Hydraulic Analyses
… of particular interest due to their relatively low upfront capital cost, scalability, and enhanced safety features. Of SMR concepts, General Electric Hitachi Nuclear Energy’s (GEH) BWRX-300 design is one of the most promising, with several countries strongly considering its viability. The …
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Validation of Plant Buzz Operational Data Using Serpent-DYN3D Sequence
… design and modeling of alternative high-assay low-enriched fuel cycles with longer cycle lengths. An established computational sequence for modeling core behavior during the fuel cycle irradiation period involves the use of lattice codes followed by a nodal diffusion core solver. In this …
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Reactor configurations to support advanced material research
… This required the consideration of high and low-power levels alongside advanced fuel with high physical density and low enriched <sup>235</sup>U. Selected fuel was U-10Mo with 19.75% <sup>235</sup>U enrichment. The fuel and control rods system geometries were adopted from Missouri S&T Reactor …
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Plutoniumfingerabdrücke und Brennstoffzyklusstudien für thermische Reaktorkonzepte
… simulation code VSOP. The fuel cycles of LEU (Low-Enriched Uranium), MOX (Mixed Oxide Fuel), ThHEU (Thorium High-Enriched Uranium) and ThPu (Thorium-Plutonium) as well as the reactor concepts of LWR, MAGNOX, CANDU, RBMK and HTR are considered within this thesis. For each combination of fuel and …
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