EDITORIAL
Published on 04 Mar 2022
Editorial: Reactor Fuels, Materials and Systems Under Extreme Environments
doi 10.3389/fenrg.2022.860553
- 1,051 views
- Frontiers in Energy Research
- Nuclear Energy
- Research Topics
- Reactor Fuels, Materials and Systems under Extreme Environments
Reactor Fuels, Materials and Systems under Extreme Environments
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Articles
REVIEW
Published on 04 Mar 2022
Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments
doi 10.3389/fenrg.2022.766865
- 6,587 views
- 12 citations
ORIGINAL RESEARCH
Published on 24 Jan 2022
Macro-Mesoscale In-Pile Thermal-Mechanical Behavior Simulation of a UMo/Zr Monolithic Fuel Plate
doi 10.3389/fenrg.2021.801398
- 904 views
- 2 citations
ORIGINAL RESEARCH
Published on 15 Oct 2021
Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System
doi 10.3389/fenrg.2021.732801
- 2,390 views
- 6 citations
ORIGINAL RESEARCH
Published on 28 Sep 2021
Experimental Investigation on the Cleaning Effect and Influence Rule of Hydrogen Peroxide–Acetic Acid on Lead–Bismuth Eutectic Alloy
doi 10.3389/fenrg.2021.735199
- 2,282 views
- 4 citations
ORIGINAL RESEARCH
Published on 21 Sep 2021
3-Dimensional Multiphysics Modeling of Behaviors of Pressurized Water Reactor Fuel Rods With Missing Pellet Surface
doi 10.3389/fenrg.2021.738084
- 1,871 views
- 2 citations
ORIGINAL RESEARCH
Published on 06 Sep 2021
Study on Thermophysical Properties of a Lead–Bismuth-Based Graphene Nanofluid
doi 10.3389/fenrg.2021.727447
- 1,595 views
- 5 citations
ORIGINAL RESEARCH
Published on 25 Aug 2021
Formation of Bubble-Loop Complexes During Helium Radiation in Fe-9Cr Steel
doi 10.3389/fenrg.2021.710907
- 1,222 views
ORIGINAL RESEARCH
Published on 30 Jul 2021
Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor
doi 10.3389/fenrg.2021.711916
- 3,113 views
- 7 citations
ORIGINAL RESEARCH
Published on 27 Jul 2021
Hydrogen Atom and Molecule Adsorptions on FeCrAl (100) Surface: A First-Principle Study
doi 10.3389/fenrg.2021.713493
- 2,135 views
- 11 citations
ORIGINAL RESEARCH
Published on 27 Jul 2021
Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program
doi 10.3389/fenrg.2021.705944
- 2,075 views
- 2 citations
ORIGINAL RESEARCH
Published on 23 Jul 2021
Giga-Cycle Fatigue Behavior of the Nuclear Structure of 316L Weldments
doi 10.3389/fenrg.2021.696608
- 1,273 views
- 2 citations
