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Showing 1 to 20 of 24 for “"HTGR"”.

  1. A reactor physics framework to detect anomalies in HTGR core

    … in High Temperature Gas-cooled Reactors (HTGRs). Neutron noise is defined as the fluctuations in the neutron detector signal caused by perturbations in a nuclear reactor. Neutron noise analysis is performed by obtaining the neutron flux signals in the time domain, which is then converted …

    uiuc Repository record for A reactor physics framework to detect anomalies in HTGR core (opens in a new tab)

  2. Impact of nuclear data libraries for criticality calculation of HTGR

    … for High-Temperature Gas-cooled Reactors (HTGR). Accurate nuclear data is essential for reactor safety analysis. However, previous studies have reported significant differences in calculated keff for HTGR systems when different nuclear data libraries are employed. This discrepancy can be …

    uiuc Repository record for Impact of nuclear data libraries for criticality calculation of HTGR (opens in a new tab)

  3. Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors.

    Thesis. 1978. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors. (opens in a new tab)

  4. Conceptual Structural Design of Core Components for a Horizontal, Compact HTGR

    … oriented High Temperature Gas Reactor (HTGR) concept and its core components. HTGRs hold significant potential in decarbonizing industrial process heat markets. Collaborators at MIT recently introduced the Horizontal, Compact HTGR (HC-HTGR), which expects to see a 20% reduction in …

    mit Repository record for Conceptual Structural Design of Core Components for a Horizontal, Compact HTGR (opens in a new tab)

  5. Conceptual design of an HTGR system for a total energy application.

    Thesis. 1975. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Conceptual design of an HTGR system for a total energy application. (opens in a new tab)

  6. Effects of fuel particle and reactor core design on modular HTGR source terms

    Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1987.

    mit Repository record for Effects of fuel particle and reactor core design on modular HTGR source terms (opens in a new tab)

  7. Exploring the improvement of HTGR economics with heat storage for variable electricity output at base-load operations

    … design is integrated into the primary loop of an HTGR reactor to minimize the use of inefficient heat exchangers. The proposed system is connected to the reactor outlet and inlet and operates a separate turbine loop once charged. The heat storage media is chosen to be ceramic brick made of alumina …

    mit Repository record for Exploring the improvement of HTGR economics with heat storage for variable electricity output at base-load operations (opens in a new tab)

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

    … 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 volume. This benefit comes with a trade-off in control system design that requires the …

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

  9. Analyzing FLUENT CFD models and data to develop fundamental codes to assess the effects of graphite oxidation in an HTGR air ingress accident

    The primary product of this thesis is a faster running computer code to model air ingress events in high temperature gas reactors as a potential subroutine for nodal codes such as MELCOR to model air ingress events. Because of limitations found in FLUENT, and the limitations of the data set, a …

    mit Repository record for Analyzing FLUENT CFD models and data to develop fundamental codes to assess the effects of graphite oxidation in an HTGR air ingress accident (opens in a new tab)

  10. High temperature creep behavior of Inconel 617 and Haynes 230

    The high temperature gas-cooled reactor (HTGR) has been selected for the Next Generation Nuclear Plant (NGNP) project. The structural materials of HTGR will serve in the temperature range of 760-950oC and withstand coolant pressure up to 7 MPa for a design life of 60 years. Currently, Ni-based …

    uiuc Repository record for High temperature creep behavior of Inconel 617 and Haynes 230 (opens in a new tab)

  11. Radiation Shielding Design and Radioactive Waste Assessment of Horizontal Compact High Temperature Gas-Cooled Reactor

    … small High Temperature Gas-Cooled Reactors (HTGRs) can provide economic, environmentally favorable and reliable electricity and heat for community and industrial purposes, Boston Atomics LLC initiated the design of Horizontal Compact HTGR (HC-HTGR). This work addresses shielding, activation …

    mit Repository record for Radiation Shielding Design and Radioactive Waste Assessment of Horizontal Compact High Temperature Gas-Cooled Reactor (opens in a new tab)

  12. Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences

    … stability at temperatures well above HTGR operating conditions. However, in the case of an air ingress accident, the oxygen introduced into the core can affect the integrity of the fuel graphite matrix. In this work a combination of computational models and mixed effects experiments …

    ksu Repository record for Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences (opens in a new tab)

  13. Design for Cost Methodology Applied to High Temperature Gas-Cooled Reactors

    … nuclear reactor architecture called the Class A HTGR (CA-HTGR), where Class A refers to the passive safety class during decay heat cooling. The architecture is used in a coupled design and cost approach to search for Levelized Cost of Electricity (LCOE) minimizing designs. The feasibility and …

    mit Repository record for Design for Cost Methodology Applied to High Temperature Gas-Cooled Reactors (opens in a new tab)

  14. Modelling of Graphite Elements and Low Enriched Fuel Assemblies for a High Temperature Gas-Cooled Reactor

    … Compact High Temperature Gas-cooled Reactor (HC-HTGR), which Boston Atomics is seeking to commercialize. The HC-HTGR leverages the safety advantages of gas- cooled, TRISO fuelled reactors, and the economic advantages of a horizontal compact layout. Graphite assembly blocks create the channels …

    mit Repository record for Modelling of Graphite Elements and Low Enriched Fuel Assemblies for a High Temperature Gas-Cooled Reactor (opens in a new tab)

  15. Surface degradation and creep of Inconel 617 and Haynes 230 at high temperatures

    The high temperature gas-cooled reactor (HTGR) design has been selected for the Next Generation Nuclear Plant (NGNP) project. The helium coolant in the primary circuit has been found to contain low levels of impurities (e.g. CO, CO2, H2O, CH4, and H2) after steady-state operation. This can lead to …

    uiuc Repository record for Surface degradation and creep of Inconel 617 and Haynes 230 at high temperatures (opens in a new tab)

  16. An integrated performance model for high temperature gas cooled reactor coated particle fuel

    … and deployment of High Temperature Gas Reactor (HTGR) systems for future power generation. Fuel performance modeling is indispensable for understanding the physical behavior of fuel particles and achieving their high reliability during operations and accidents through a guided design process. …

    mit Repository record for An integrated performance model for high temperature gas cooled reactor coated particle fuel (opens in a new tab)

  17. The flow structure under mixed convection in a uniformly heated vertical pipe

    … the high temperature gas-cooled thermal reactor (HTGR), the decay heat removal (DHR) in depressurization accidents is a major challenge to be overcome. This is due to (1) a gas has inherently inferior heat transport capabilities compared to a liquid and (2) the high surface heat flux of the GFR …

    mit Repository record for The flow structure under mixed convection in a uniformly heated vertical pipe (opens in a new tab)

  18. Investigation of MELCOR and STAR-CCM+ modeling capabilities to accurately predict air ingress rates from small breaks in high temperature gas-cooled reactors

    In a High Temperature Gas-cooled Reactor (HTGR), the study of postulated accident scenarios is necessary for licensing, deployment, and public perception. One specific scenario of concern is the air ingress following a primary loop break. Recent research has determined that small breaks are more …

    uiuc Repository record for Investigation of MELCOR and STAR-CCM+ modeling capabilities to accurately predict air ingress rates from small breaks in high temperature gas-cooled reactors (opens in a new tab)

  19. Isotopic and reactor physics characterization of a gas-cooled, pebble-bed microreactor

    Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2022-11-11 without embargo terms

    uiuc Repository record for Isotopic and reactor physics characterization of a gas-cooled, pebble-bed microreactor (opens in a new tab)

  20. CFD Analyses of Flow Structures in Air-Ingress and Rod Bundle Problems

    Two topics from nuclear engineering field are included in this dissertation. One study is the air-ingress phenomenon during a loss of coolant accident (LOCA) scenario, and the other is a 5-by-5 bundle assembly problem under a design of PWRs. The objectives are to investigate the Kelvin-Helmholtz …

    tdl Repository record for CFD Analyses of Flow Structures in Air-Ingress and Rod Bundle Problems (opens in a new tab)

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