Global ETD Search
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 9 of 9 for “"Molten Salt Reactor (MSR)"”.
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One-dimensional single phase natural circulation model of FLiNaK in Molten Salt Loop
This work studied a coolant for a molten salt type reactor in terms of a natural circulation behavior. A natural circulation model using MATLAB was developed. This model is for the Molten Salt Loop currently under development at University of Ontario Institute of Technology to investigate aging …
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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 …
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Development of a Minichannel Compact Primary Heat Exchanger for a Molten Salt Reactor
The first Molten Salt Reactor (MSR) was designed and tested at Oak Ridge National Laboratory (ORNL) in the 1960's, but recent technological advancements now allow for new components, such as heat exchangers, to be created for the next generation of MSR's and molten salt-cooled reactors. The primary …
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Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle
<p>"Molten salt reactor (MSR) is one of six reactors selected by the Generation IV International Forum (GIF). The liquid fluoride thorium reactor (LFTR) is a MSR concept based on thorium fuel cycle. LFTR uses liquid fluoride salts as a nuclear fuel. It uses <sup>232</sup>Th and <sup>233</sup>U as …
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Quantifying the adhesion of noble metal foulants on structural materials in a Molten Salt Reactor
As discovered during the Molten Salt Reactor (MSR) Experiment (MSRE), selected fission products deposited on the wetted surfaces throughout the reactor. Fission products such as molybdenum and ruthenium are noble with respect to the electrochemical potential of the fluoride fuel salt and therefore …
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Consideration of fuel behaviour in AGR-like FHR reactor design
The Fluoride Salt-cooled High-temperature Reactor (FHR) is a subclass of Molten Salt Reactor (MSR) that uses solid fuel separated from the molten coolant salt. Previous work showed that British Advance Gas-cooled Reactor (AGR) technology can be used to potentially reduce the time required to …
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Reduction of Solid Uranium Dioxide in Calcium Salts
… fuel through burn-up in the Generation IV reactor designs, one of which is the molten salt reactor (MSR). Therefore, the MSR can use the spent nuclear fuel as a fresh fuel when the actinides recycle. That reprocessing of spent fuel could be one of the opportunities to contribute to future …
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Studies on Molten Salt Fuels: Properties, Purification, and Materials Degradation
The molten salt reactor (MSR) is one of the advanced nuclear reactors expected to be alternatives to the conventional water-cooled nuclear reactor systems. Despite many advantages of MSRs, properties of molten salts have not been sufficiently measured in previous studies. In addition, the corrosion …
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FLOW VISUALIZATION OF TWO-PHASE FLOW IN MOLTEN-SALT: HELIUM BUBBLING IN LITHIUM FLUORIDE - SODIUM FLUORIDE - POTASSIUM FLUORIDE (LIF- NAF- KF)
… two-phase flow visualization experiments in molten salt. A stainless-steel 316 (SST316) test apparatus equipped with a clear quartz section was designed to conduct visualization experiments of single helium bubbles rising in fluoride salt within a temperature range of 460 – 650 °C. The …