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Light-water reactor
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Keyword
keyword
Light-water reactor
RIS
0.001
(Research Intensity Score)
Papers
309
Top papers
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms
2021 · 251 citations
Materials for future nuclear energy systems
2019 · 361 citations
Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings
2021 · 129 citations
Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
2019 · 387 citations
Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods
2024 · 15 citations
Corrosion of zirconium fuel cladding inside a boiling water reactor: A post-irradiation study by atom probe tomography
2025 · 9 citations
Radiation Damage in Nuclear Materials – Series #8 High-Entropy Alloys (HEAs): Engineering Radiation-Resistant Materials for Extreme Nuclear
2026
Radiation Damage in Nuclear Materials – Series #8 High-Entropy Alloys (HEAs): Engineering Radiation-Resistant Materials for Extreme Nuclear
2026
GIFT-1.0: Advanced light water reactor fuel performance code
2025 · 4 citations
Newest papers
Radiation Damage in Nuclear Materials – Series #8 High-Entropy Alloys (HEAs): Engineering Radiation-Resistant Materials for Extreme Nuclear
2026
Radiation Damage in Nuclear Materials – Series #8 High-Entropy Alloys (HEAs): Engineering Radiation-Resistant Materials for Extreme Nuclear
2026
Irradiation-Assisted Stress Corrosion Cracking (IASCC) - When Radiation, Stress, and Water Chemistry Combine
2026
Irradiation-Assisted Stress Corrosion Cracking (IASCC) - When Radiation, Stress, and Water Chemistry Combine
2026
NEUTRONICS AND THERMAL-HYDRAULICS OF PRESSURIZED WATER REACTOR WITH THORIUM-BASED FUEL
2026
Modern Light Water Nuclear Reactors of Generation III+ and Small Modular Reactors: Challenges and Solutions in the Field of Nuclear Fuel and Management
2026
Neutronic Assessment of Advanced Fuels and Moderators for Enhanced Light Water Reactor (LWR) Safety and Performance
2026
Upgrade of FROBA code to derive new insights in fuel performance of Lead-Bismuth Eutectic Cooled Fast Reactor
2026 · 1 citations
Probabilistic Failure Analysis of SiC‐CMC/Nb Fuel Claddings Under Loss‐Of‐Coolant Accident Conditions
2026
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