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Showing 1 to 20 of 23 for “"Advanced Reactors"”.

  1. Mechanical characterization of alloy 709 stainless steel after high temperature aging for application in advanced reactors

    Sodium fast reactors are among the leading generation IV nuclear reactor designs being studied for future development. They will 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, …

    uiuc Repository record for Mechanical characterization of alloy 709 stainless steel after high temperature aging for application in advanced reactors (opens in a new tab)

  2. Simulation of the nuclear fuel cycle with recycling : options and outcomes

    … cycle, and the impact of different options for advanced reactors and fuel recycling facilities on the accumulation of the transuranics (TRU) inventory. Several aspects of the nuclear fuel cycle are studied for the US and for Brazil. This includes the impact of advanced nuclear technologies' …

    mit Repository record for Simulation of the nuclear fuel cycle with recycling : options and outcomes (opens in a new tab)

  3. Pathways and frameworks for the licensing and regulation of advanced nuclear reactors in the United States

    … a challenge for the licensing and deployment of advanced nuclear power plants. These advanced nuclear power plants can utilize passive systems, new fuel forms or coolants, or other new design features to accomplish their safety and security functions. Advanced reactors may not comply with …

    mit Repository record for Pathways and frameworks for the licensing and regulation of advanced nuclear reactors in the United States (opens in a new tab)

  4. Investigation into the Processing Parameters of Phosphate-based Dechlorination of Electrorefiner Salt Waste

    … be applied to waste from our current fleet or reactors, as well as advanced reactors in which pilot-scale facilities are currently being evaluated. In this study, a procedure was developed for the dechlorination of an electrorefiner salt waste simulant called ERV3 salt based on the results of …

    unr Repository record for Investigation into the Processing Parameters of Phosphate-based Dechlorination of Electrorefiner Salt Waste (opens in a new tab)

  5. Fuel cycle transition simulation capabilities in CYCLUS

    Recent interest in advanced reactors and the following need for techno-economic transitions has increased the demand for tools necessary to model complex nuclear fuel cycles (NFCs) and advanced reactor technologies. This thesis demonstrates the capability of CYCLUS , the agent-based fuel cycle …

    uiuc Repository record for Fuel cycle transition simulation capabilities in CYCLUS (opens in a new tab)

  6. Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system

    … must be considered during the design of an advanced reactor. However, an advanced reactor's core damage frequency dominates all other considerations at the preliminary stage of reactor design. An iterative four-step methodology to guide the MIT gas-cooled fast reactor emergency core cooling …

    mit Repository record for Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system (opens in a new tab)

  7. The use for frequency-consequence curves in future reactor licensing

    … plants has focused until now on Light Water Reactors and has not incorporated systematically insights and benefits from Probabilistic Risk Assessment (PRA). With the goal of making the licensing process more efficient, predictable and stable for advanced reactors, the U.S. Nuclear Regulatory …

    mit Repository record for The use for frequency-consequence curves in future reactor licensing (opens in a new tab)

  8. Assessment of Hybrid CFD Turbulence Model, STRUCT-epsilon, for Thermal Striping Behavior

    Many advanced nuclear reactor designs are susceptible to thermal fatigue damage caused by thermal striping, which presently accepted modeling and design tools are unable to accurately or reliably predict the presence of. Advanced reactors are vital in achieving net-zero carbon electricity …

    mit Repository record for Assessment of Hybrid CFD Turbulence Model, STRUCT-epsilon, for Thermal Striping Behavior (opens in a new tab)

  9. Neutronic Analysis of Horizontal-Compact High Temperature Gas-cooled Reactor

    … the significant cost challenges associated with advanced reactors, a 150MWt horizontal compact high temperature gas-cooled reactor (HC-HTGR) has been proposed. The HC-HTGR has potential to reduce the capital cost of a traditional vertical oriented HTGR by 20% through reduction in reactor building …

    mit Repository record for Neutronic Analysis of Horizontal-Compact High Temperature Gas-cooled Reactor (opens in a new tab)

  10. Fuel cycle options for optimized recycling of nuclear fuel

    … spent nuclear fuel depends on both deployment of advanced reactors that can be loaded with recycled transuranics (TRU), and on availability of the facilities that separate and reprocess spent fuel. Three recycling strategies are explored in this study: (1) Recycling in thermal Light 'Water …

    mit Repository record for Fuel cycle options for optimized recycling of nuclear fuel (opens in a new tab)

  11. Deterministic casualty analysis of the Pebble Bed Modular Reactor for use with risk-based safety regulation

    … process is also necessary in order to license advanced reactors that are not light water technology. Risk based reactor licensing, which uses the Probabilistic Risk Assessment (PRA) to justify most licensing questions, is a proposed replacement for the current methods. This work further …

    mit Repository record for Deterministic casualty analysis of the Pebble Bed Modular Reactor for use with risk-based safety regulation (opens in a new tab)

  12. Materials Design for Advanced Nuclear Energy Systems: Refractory High Entropy Alloys and Metallic Multilayer Composites

    Advanced nuclear reactors present a multitude of materials challenges due to high op- erating temperatures, corrosive environments, and neutron radiation damage. In this thesis, I focus on two approaches to designing better materials for advanced reactors, high entropy alloys (HEAs) and metallic …

    mit Repository record for Materials Design for Advanced Nuclear Energy Systems: Refractory High Entropy Alloys and Metallic Multilayer Composites (opens in a new tab)

  13. 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 …

    mit Repository record for Integrated fuel performance and thermal-hydraulic sub-channel models for analysis of sodium fast reactors (opens in a new tab)

  14. Development of a Supervisory Control System as a Transition Technology Towards Autonomous Reactor Plant Operations

    The economic viability of small and microreactors depends on reducing energy generation costs. The implementation of autonomous reactor control systems provides an avenue for reducing operations and maintenance expenses. Advanced reactor designs with enhanced passive safety features, reduced source …

    mit Repository record for Development of a Supervisory Control System as a Transition Technology Towards Autonomous Reactor Plant Operations (opens in a new tab)

  15. Thermal Properties of Candidate Coolant Salts

    With the increasing research on advanced reactors, molten salt reactors have been recognized for their potential. As with any advanced reactor concept, each component and material must be thoroughly investigated before any reactors of that type are created. One of the most pressing issues in MSR …

    vt Repository record for Thermal Properties of Candidate Coolant Salts (opens in a new tab)

  16. 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

    uiuc Repository record for Investigation of the impacts of deploying reactors fueled by high-assay low enriched uranium (opens in a new tab)

  17. Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation

    … has become more urgent for the simulation of advanced reactors and monitoring and safeguards of spent fuel pools. To this end, the Virginia Tech Transport Theory Group (VT3G) has been working on advanced computational tools for accurate modeling and simulation of nuclear systems in real-time. …

    vt Repository record for Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation (opens in a new tab)

  18. A First Complete Approach to Address Model Error in Computational Turbulent Heat Transfer

    … see as a crucial step enabling licensing of advanced reactors such as liquid metal cooled and molten salt cooled reactors.

    mit Repository record for A First Complete Approach to Address Model Error in Computational Turbulent Heat Transfer (opens in a new tab)

  19. An Investigation of Major Component Disposal Costs for Advanced Nuclear Reactors

    … NPP fleet is exclusively made of light water reactors and as such there are no detailed study of decommissioning for advanced reactors that are being developed for deployment. This work modelled activity and benchmarked the disposal costs for a Pressurized Water Reactor’s (PWR) components …

    mit Repository record for An Investigation of Major Component Disposal Costs for Advanced Nuclear Reactors (opens in a new tab)

  20. Rotating Disk Electrode Design for Concentration Measurements in Flowing Molten Chloride Salts

    … a metal-based fuel that could be used in certain advanced reactors. Molten salt reactors are of particular interest when it comes to reprocessing spent nuclear fuel because of their unique property of using a liquid fuel. Molten salt reactors and spent fuel reprocessors could be directly connected …

    vt Repository record for Rotating Disk Electrode Design for Concentration Measurements in Flowing Molten Chloride Salts (opens in a new tab)

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