Methods
Published on 17 Dec 2021
The Application of the Combined Fission Matrix Theory in Fast Reactors
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2021.766449
- 2,996 views
- 1 citation
10 articles related to "Fast Reactors"
Articles
Editorial
Published on 31 Jan 2023
Editorial: Experimental and numerical studies on liquid metal cooled fast reactors
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2023.1140962
- 2,905 views
- 1 citation
Original Research
Published on 02 May 2025
Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2025.1566271
- 2,029 views
Original Research
Published on 30 Sep 2022
Analysis of fuel performance under normal operation conditions of MicroURANUS: Micro long-life lead-bismuth-cooled fast reactor
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2022.965319
- 4,974 views
- 2 citations
Original Research
Published on 25 Feb 2021
Study of Flow and Heat Transfer Characteristics of Lead-Based Liquid Metals in a Turbulent Tube Flow and the Impacts of Roughness
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2021.634964
- 4,858 views
- 12 citations
Original Research
Published on 08 Jun 2021
Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2021.678939
- 5,164 views
- 8 citations
Original Research
Published on 05 Dec 2022
Assessing the interfacial corrosion mechanism of Inconel 617 in chloride molten salt corrosion using multi-modal advanced characterization techniques
in Nuclear Materials
Frontiers in Nuclear Engineering
doi 10.3389/fnuen.2022.1049693
- 5,721 views
- 5 citations
Original Research
Published on 03 Oct 2024
Numerical investigation on the core thermal hydraulic behavior of pool-type sodium-cooled fast reactor (SFR)
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2024.1439022
- 2,022 views
Methods
Published on 09 Jan 2023
Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo
in Nuclear Materials
Frontiers in Nuclear Engineering
doi 10.3389/fnuen.2022.1054288
- 2,859 views
- 6 citations
Original Research
Published on 18 Jul 2022
Proposal of a turbulent Prandtl number model for Reynolds-averaged Navier–Stokes approach on the modeling of turbulent heat transfer of low-Prandtl number liquid metal
in Nuclear Energy
Frontiers in Energy Research
doi 10.3389/fenrg.2022.928693
- 4,155 views
- 12 citations