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Showing 1 to 16 of 16 for “"high temperature gas cooled reactor"”.
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Neutronic Analysis of Horizontal-Compact High Temperature Gas-cooled Reactor
… 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 volume. …
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Environmental impacts of the modular high temperature gas-cooled reactor (MHTGR)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990.
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OXIDATION OF SILICON CARBIDE AND GRAPHITE FOR HIGH TEMPERATURE GAS-COOLED REACTOR APPLICATIONS
… to accident scenarios in Gen IV thermal spectrum high temperature gas cooled nuclear reactors. It is imperative to understand the oxidation behavior of such materials to predict their response to off-normal environments and certify their accident tolerance to implement Gen IV reactors. The onset …
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An integrated performance model for high temperature gas cooled reactor coated particle fuel
… essential for the development 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 …
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Elevated Temperature Oxidation Behavior and Mechanical Properties of High Temperature Gas Cooled Reactor Materials
Made available in DSpace on 2017-07-06T18:55:31Z (GMT). No. of bitstreams: 3 Nagarathnam_Karthikeyan_MS.pdf: 120520263 bytes, checksum: 3e0eb2457be7fdfc7e531cbc3263cf05 (MD5) Nagarathnam_Karthikeyan_MS_ABS.pdf: 1198387 bytes, checksum: 23b15010e2eebe8cd6f4ba495ce3ff33 (MD5) license.txt: 4813 bytes, …
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Development of a High Temperature Gas-Cooled Reactor TRISO-coated particle fuel chemistry model
… analysis of the chemical environment in a High Temperature Gas-Cooled Reactor TRISO fuel particle. Fission product inventory versus burnup is calculated. Based on those results a thermodynamic analysis is performed to determine fission product vapor pressures, oxygen partial pressure, and …
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Benchmarking of the MIT High Temperature Gas-cooled Reactor TRISO-coated particle fuel performance model
MIT has developed a Coated Particle Fuel Performance Model to study the behavior of TRISO nuclear fuels. The code, TIMCOAT, is designed to assess the mechanical and chemical condition of populations of coated particles and to determine the failure probability of each of the structural coating …
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Radiation Shielding Design and Radioactive Waste Assessment of Horizontal Compact High Temperature Gas-Cooled Reactor
… that nuclear power plants utilizing 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 …
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Modelling of Graphite Elements and Low Enriched Fuel Assemblies for a High Temperature Gas-Cooled Reactor
… costs and risk of large Pressurized Water Reactors (PWRs), Stewart et al. designed a Horizontal 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 …
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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 …
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A quantitative assessment of nuclear weapons proliferation risk utilizing probabilistic methods
… proliferation risk between various nuclear reactor/fuel cycle concepts using a probabilistic method. The work presented details quantified proliferation resistance metrics of a pressurized water reactor (PWR), a PWR utilizing thorium as a fertile component of the nuclear fuel (Radkowsky …
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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 …
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Waste characteristics of spent nuclear fuel from a pebble bed reactor
… characteristics and disposal aspects between a high-temperature, gas cooled, reactor with a pebble bed core (PBR) and a pressurized water reactor (PWR). There are three significant differences which impact the disposal characteristics of PBR spent pebble fuel from PWR spent fuel assemblies. …
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CFD Modeling and Simulation of Natural Circulation in Helium- Cooled Very High Temperature Reactors
… behavior of natural circulation in helium-cooled Very High Temperature Reactor (VHTR) systems, focusing on the performance and validation of passive safety features under Pressurized or Depressurized Loss of Forced Cooling (P-LOFC or D-LOFC) events. An experimental facility inspired by the …
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1D and 3D simulation of a water cooled reactor cavity cooling system experimental facility
The fourth-generation nuclear reactors have many safety features, including the reactor cavity cooling system (RCCS). This system is intended to remove decay heat from the reactor cavity. Designs exist for both air-cooled and water-cooled configurations. It operates completely passively and is …
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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 …