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Neutron moderator
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Keyword
keyword
Neutron moderator
RIS
0.000
(Research Intensity Score)
Papers
77
Top papers
Calculation and influence study of moderator thermal neutron scattering cross section of beam shaping assembly in AB-BNCT
2026 · 1 citations
Design of a versatile and compact moderator for the CNA HiSPANoS neutron source
2026
Nuclear Reactor Physics and Radiation Transport in Advanced Fission Systems: Neutron Moderation, Criticality, and Isotopic Burn-up in Thermal and Fast Reactor Environments (2000–2026)
2026
Nuclear Reactor Physics and Radiation Transport in Advanced Fission Systems: Neutron Moderation, Criticality, and Isotopic Burn-up in Thermal and Fast Reactor Environments (2000–2026)
2026
Nuclear Reactor Physics and Radiation Transport in Advanced Fission Systems: Neutron Moderation, Criticality, and Isotopic Burn-up in Thermal and Fast Reactor Environments (2000–2026)
2026
Beryllium oxide utilized in nuclear reactors: Part I: Application history, thermal properties, mechanical properties, corrosion behavior and fabrication methods
2022 · 35 citations
Development and potential of composite moderators for elevated temperature nuclear applications
2022 · 47 citations
Optimization of Target Materials for a 3 MeV Proton-Driven Accelerator Neutron Source for Boron Neutron Capture Therapy
2026
Design and optimization of an accelerator-based neutron source for BNCT using Geant4 Monte Carlo simulations
2025 · 1 citations
Newest papers
Calculation and influence study of moderator thermal neutron scattering cross section of beam shaping assembly in AB-BNCT
2026 · 1 citations
Design of a versatile and compact moderator for the CNA HiSPANoS neutron source
2026
Nuclear Reactor Physics and Radiation Transport in Advanced Fission Systems: Neutron Moderation, Criticality, and Isotopic Burn-up in Thermal and Fast Reactor Environments (2000–2026)
2026
Nuclear Reactor Physics and Radiation Transport in Advanced Fission Systems: Neutron Moderation, Criticality, and Isotopic Burn-up in Thermal and Fast Reactor Environments (2000–2026)
2026
Nuclear Reactor Physics and Radiation Transport in Advanced Fission Systems: Neutron Moderation, Criticality, and Isotopic Burn-up in Thermal and Fast Reactor Environments (2000–2026)
2026
Optimization of Target Materials for a 3 MeV Proton-Driven Accelerator Neutron Source for Boron Neutron Capture Therapy
2026
Design and optimization of an accelerator-based neutron source for BNCT using Geant4 Monte Carlo simulations
2025 · 1 citations
Determination of the Neutron Fluxes Energy Spectrum of the WWR-SM Reactor of the INP AS RU
2025
Evaluating the Use of Graphite and BeO Moderators for Micro Molten Salt Reactor
2025
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