Found: 13
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Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor.
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- EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/e2015-50032-6
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- Article
Evaluation of Transport–Burnup Coupling Strategy in Double-Heterogeneity Problem.
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- Energies (19961073), 2024, v. 17, n. 15, p. 3792, doi. 10.3390/en17153792
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- Article
Comparative Irradiated Dimensional Change Strain Analyses of Two Types of Graphite Components in a Thorium Molten Salt Reactor.
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- Energies (19961073), 2024, v. 17, n. 11, p. 2469, doi. 10.3390/en17112469
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- Article
Comparative Study on the Neutronic Performance of Thermal and Fast Molten Salt Reactors under Once-Through Fuel Cycle.
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- International Journal of Energy Research, 2023, v. 2023, p. 1, doi. 10.1155/2023/8875215
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- Article
Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies.
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- International Journal of Energy Research, 2021, v. 45, n. 8, p. 12147, doi. 10.1002/er.6168
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- Article
Spent fuel characteristics for thorium‐uranium recycle in fluoride‐salt‐cooled solid‐fuel fast reactor.
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- International Journal of Energy Research, 2021, v. 45, n. 8, p. 12413, doi. 10.1002/er.6619
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- Article
Neutronic effect of graphite dimensional change in a small modular molten salt reactor.
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- International Journal of Energy Research, 2021, v. 45, n. 8, p. 11976, doi. 10.1002/er.5964
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- Article
Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor.
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- International Journal of Energy Research, 2020, v. 44, n. 10, p. 8062, doi. 10.1002/er.5004
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- Article
Low enriched uranium and thorium fuel utilization under once‐through and offline reprocessing scenarios in small modular molten salt reactor.
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- International Journal of Energy Research, 2019, v. 43, n. 11, p. 5775, doi. 10.1002/er.4676
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- Article
Core Optimization for Extending the Graphite Irradiation Lifespan in a Small Modular Thorium-Based Molten Salt Reactor.
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- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 2, p. 168, doi. 10.3390/jne5020012
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- Article
Neutron/Gamma Radial Shielding Design of Main Vessel in a Small Modular Molten Salt Reactor.
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- Journal of Nuclear Engineering (JNE), 2023, v. 4, n. 1, p. 213, doi. 10.3390/jne4010017
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- Article
The Study of Continuous Core Zoning to Extend the Graphite Component Irradiation Lifespan in Molten Salt Reactor.
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- International Journal of Energy Research, 2024, v. 2024, p. 1, doi. 10.1155/2024/4941827
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- Article
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library.
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- Science & Technology of Nuclear Installations, 2024, v. 2024, p. 1, doi. 10.1155/2024/3612655
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- Article