ORIGINAL RESEARCH
Published on 02 Sep 2022
Numerical investigation of heat transfer characteristics of moderator assembly employed in a low-enriched uranium nuclear thermal propulsion reactor
doi 10.3389/fenrg.2022.875371
- 2,152 views
- Frontiers in Energy Research
- Nuclear Energy
- Research Topics
- Numerical Methods and Computational Sciences Applied to Nuclear Energy
Numerical Methods and Computational Sciences Applied to Nuclear Energy
3,687
Total downloads
24k
Total views and downloads
Submit your idea
You will be redirected to our submission process.
Articles
ORIGINAL RESEARCH
Published on 10 Aug 2022
An iDTMC-based Monte Carlo depletion of a 3D SMR with intra-pin flux renormalization
doi 10.3389/fenrg.2022.859622
- 1,425 views
- 3 citations
ORIGINAL RESEARCH
Published on 05 May 2022
An Improved Model of the Heat Pipe Based on the Network Method Applied on a Heat Pipe Cooled Reactor
doi 10.3389/fenrg.2022.848799
- 2,517 views
- 7 citations
ORIGINAL RESEARCH
Published on 27 Apr 2022
Improved Radiation Heat Transfer Model in RELAP5 for Compact Fuel Rod Bundles by the Absorption Factor Modification
doi 10.3389/fenrg.2022.841631
- 838 views
- 3 citations
ORIGINAL RESEARCH
Published on 20 Apr 2022
Scalability of Nek5000 on High-Performance Computing Clusters Toward Direct Numerical Simulation of Molten Pool Convection
doi 10.3389/fenrg.2022.864821
- 1,554 views
- 1 citation
ORIGINAL RESEARCH
Published on 13 Apr 2022
Investigation of Nodal Numerical Adjoints From CMFD-Based Acceleration Methods
doi 10.3389/fenrg.2022.873731
- 633 views
- 1 citation
ORIGINAL RESEARCH
Published on 23 Mar 2022
Mechanical Feasibility Analysis of the Surface Microstructure to Be Used in the Nuclear Reactor
doi 10.3389/fenrg.2022.843212
- 882 views
ORIGINAL RESEARCH
Published on 18 Mar 2022
Pin-by-Pin Coupled Transient Monte Carlo Analysis Using the iMC Code
doi 10.3389/fenrg.2022.853222
- 1,307 views
- 2 citations
ORIGINAL RESEARCH
Published on 17 Mar 2022
Effects of Matrix Creep Properties on Effective Irradiation Swelling of U-10Mo/Zr Dispersion Nuclear Fuels
doi 10.3389/fenrg.2022.851747
- 1,167 views
- 1 citation
ORIGINAL RESEARCH
Published on 14 Feb 2022
Vessel Failure Analysis of a Boiling Water Reactor During a Severe Accident
doi 10.3389/fenrg.2022.839667
- 2,888 views
- 4 citations
ORIGINAL RESEARCH
Published on 10 Feb 2022
Numerical Study on the Effect of Jet Cross Section Shape on the Corium Jet Breakup Behavior With Lattice Boltzmann Method
doi 10.3389/fenrg.2022.834237
- 1,335 views
- 3 citations
ORIGINAL RESEARCH
Published on 02 Dec 2021
Validation of Doppler Temperature Coefficients and Assembly Power Distribution for the Lattice Code KYLIN V2.0.
doi 10.3389/fenrg.2021.801481
- 2,889 views
- 5 citations
Published in
Frontiers in Energy Research
- Nuclear Energy
Impact
- 24kTopic views
- 19kArticle views
- 3,687Article downloads