Weiju Ren Senior Scientist Contact renw@ornl.gov | 865.576.6402 All Publications Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database Path Forward: Materials Data Modernization for ASME Codes and Standards in the Artificial Intelligence Era Demystify the 1.1 Factor for Ultimate Tensile Strength Above Room Temperature in Development of the Code Stress Tables... Thermal Aging Effects on the Yield and Tensile Strength of 9Cr-1Mo-V (Grade 91)... A Discussion of Strength Reduction Factor Development for Thermal Aging Effect on Nuclear Structural Alloys... Oak Ridge National Laboratory Technical Input for the Nuclear Regulatory Commission Review of the 2017 Edition of ASME Sectio... ALLOY SELECTION AND C-276 CODE DESIGN VALUE EXTENSION FOR ADVANCED MOLTEN SALT TECHNOLOGY TEST FACILITIES EXPERIMENTATION... Consideration of Thermal Embrittlement in Alloy 316H for Advanced Non-Light Water Reactor Applications... Phenomena Identification and Ranking Table (PIRT) study for metallic structural materials for advanced High-Temperature reactor Considerations of Alloy N Code Extension for Commercial Molten Salt Reactor Development and Deployment Current Status of the ASME Materials Properties Database Development... “materials & Fabrication,” 2016 Proceedings of the Asme Pressure Vessels and Piping Conference, Volume Vi The Significance of the Tertiary Creep Criterion in Setting Time-Dependent Allowable Stresses... Interoperability of Materials Database Systems in Support of Nuclear Energy Development and Potential Applications for Fuel C... Status of Alloy 800H in Considerations for the Gen IV Nuclear Energy Systems... MATERIALS PROPERTY DATABASE DEVELOPMENT FOR ASME CODES AND STANDARDS... PHASE I MATERIALS PROPERTY DATABASE DEVELOPMENT FOR ASME CODES AND STANDARDS... Consideration of Ecosystem for ICME... Effective Materials Property Information Management for the 21st Century... Considerations of Alloy N for Fluoride Salt-Cooled High-Temperature Reactor Applications... Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems - Part II: Metallurgical Property Challenges... A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems... Effective Materials Property Information Management for the 21st Century... Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems - Part I: Mechanical Property Challenges... Developing a Nuclear Grade of Alloy 617 for Gen IV Nuclear Energy Systems... Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Interview with Dr. Weiju Ren on Knowledgebase Power for Nuclear Energy Developm… Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Mechanical Properties and Mechanics Group
