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Neutron transport
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Keyword
keyword
Neutron transport
RIS
0.002
(Research Intensity Score)
Papers
415
Top papers
Nuclear technology considerations and neutronics for the ST-E1 fusion power plant
2026 · 7 citations
Thermal Energy Transport in Oxide Nuclear Fuel
2021 · 89 citations
Summary of researches on operational characteristics and safety of molten salt fast reactors based on neutronics and thermal-hydraulics coupling analysis
2025 · 12 citations
Exploratory thermal and fluid-dynamic assessment of a pin of the Helium cooled pebble bed breeding blanket concept with a modular pin monoblock design for the EU DEMO nuclear fusion reactor
2025 · 7 citations
Breeder blanket and tritium fuel cycle feasibility of the Infinity Two fusion pilot plant
2025 · 10 citations
Development and application of a coupled point-reactor and multi-channel delayed neutron precursor transport model in molten salt reactors
2026
Neutronics analysis and design of mechanical shim control strategy for a pressurized water reactors under base load operation
2026
Thorium and fully ceramic microencapsulated TRISO fuel neutronics feasibility analysis in a gas cooled fast reactor: Enhancing transmutation of long-lived fission products
2025 · 5 citations
Activation analysis and radioactive waste assessment for COOL blanket in CFETR
2026
Newest papers
Nuclear technology considerations and neutronics for the ST-E1 fusion power plant
2026 · 7 citations
Development and application of a coupled point-reactor and multi-channel delayed neutron precursor transport model in molten salt reactors
2026
Neutronics analysis and design of mechanical shim control strategy for a pressurized water reactors under base load operation
2026
Activation analysis and radioactive waste assessment for COOL blanket in CFETR
2026
Neutronics model developments for the IFMIF-DONES test cell
2026
Neutronics Analysis of a Pin-cell of VVER 1200 for Al2O3.Cr2O3.TiO2 Coated Cladding
2026
Constraints on nuclear-driven photon generation and radiation transport in extreme-energy systems
2026
Preliminary study neutronic design and optimization of a long-life gas-cooled fast reactor with modified CANDLE scheme using OpenMC
2026
Investigation of Core Neutronics in a Multi-Purpose Research Reactor Utilizing VVR-KN Fuel
2026
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