EDITORIAL
Published on 26 Jan 2021
Editorial: Advances in Nuclear Power Engineering
doi 10.3389/fenrg.2020.629655
- 2,601 views
- Frontiers in Energy Research
- Nuclear Energy
- Research Topics
- Advances in Nuclear Power Engineering
Advances in Nuclear Power Engineering
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Articles
BRIEF RESEARCH REPORT
Published on 14 Dec 2020
Experimental Study on the Natural Deposition Characteristics of Erosols in Containment
doi 10.3389/fenrg.2020.527598
- 1,525 views
- 1 citation
BRIEF RESEARCH REPORT
Published on 20 Nov 2020
Uncertainty Analysis on k-ε Turbulence Model in the Prediction of Subcooled Boiling in Vertical Pipes
doi 10.3389/fenrg.2020.584531
- 1,499 views
- 6 citations
BRIEF RESEARCH REPORT
Published on 30 Sep 2020
Scaling Design of the Pressure Response Experimental Facility for Pressure Suppression Containment
doi 10.3389/fenrg.2020.524445
- 1,310 views
- 2 citations
ORIGINAL RESEARCH
Published on 28 Sep 2020
Numerical Analysis of FLiBe Laminar Convective Heat Transfer Characteristics in Tubes Fitted With Coaxial Cross Twisted Tape Inserts
doi 10.3389/fenrg.2020.00178
- 2,465 views
- 6 citations
ORIGINAL RESEARCH
Published on 07 Sep 2020
Study on the Breakdown Mechanism of Water Film on Corrugated Plate Wall Under the Horizontal Shear of Airflow: A Short Communication
doi 10.3389/fenrg.2020.00197
- 1,366 views
- 4 citations
PERSPECTIVE
Published on 03 Sep 2020
Review and Prospect of the Measurement Technology of the Thickness of the Liquid Film on the Wall of the Corrugated Plate Dryer
doi 10.3389/fenrg.2020.00214
- 1,305 views
- 2 citations
ORIGINAL RESEARCH
Published on 27 Aug 2020
Analysis of Measuring Characteristics of the Differential Pressure Water-Level Measurement System Under Depressurization Condition
doi 10.3389/fenrg.2020.00145
- 1,466 views
- 1 citation
METHODS
Published on 19 Aug 2020
An Improved Best Estimate Plus Uncertainty Method for Small-Break Loss-of-Coolant Accident in Pressurized Water Reactor
doi 10.3389/fenrg.2020.00188
- 2,852 views
- 8 citations
BRIEF RESEARCH REPORT
Published on 21 Jul 2020
Numerical Study of the Influence of Tube Arrangement on the Flow Distribution Inside the Heat Exchanger in the PCCS
doi 10.3389/fenrg.2020.00164
- 1,754 views
- 2 citations
ORIGINAL RESEARCH
Published on 07 Jul 2020
GPU Based Two-Level CMFD Accelerating Two-Dimensional MOC Neutron Transport Calculation
doi 10.3389/fenrg.2020.00124
- 1,829 views
- 2 citations
ORIGINAL RESEARCH
Published on 02 Jul 2020
Study on Typical Design Basis Conditions of HPR1000 With Nuclear Safety Analysis Code ATHLET
doi 10.3389/fenrg.2020.00127
- 2,894 views
- 1 citation
Published in
Frontiers in Energy Research
- Nuclear Energy
Impact
- 52kTopic views
- 41kArticle views
- 8,313Article downloads