Weiju Ren Senior Scientist Contact RENW@ORNL.GOV All Publications Latent Pitfalls in Microstructure-Based Modeling for Thermally Aged 9Cr-1Mo-V Steel (Grade 91)... Path Forward: Materials Data Modernization for ASME Codes and Standards in the Artificial Intelligence Era Considerations of Alloy N Code Extension for Commercial Molten Salt Reactor Development and Deployment “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... Consideration of Ecosystem for ICME... Considerations of Alloy N for Fluoride Salt-Cooled High-Temperature Reactor Applications... 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... A REVIEW PAPER ON AGING EFFECTS IN ALLOY 617 FOR GEN IVNUCLEAR REACTOR APPLICATIONS... Status of materials handbooks for particle accelerator and nuclear reactor applications... PRELIMINARY CONSIDERATION OF ALLOYS 617 AND 230 FOR GENERATION IV NUCLEAR REACTOR APPLICATIONS... A REVIEW OF AGING EFFECTS IN ALLOY 617 FOR GEN IV NUCLEAR REACTOR APPLICATIONS ... A BRIEF REVIEW OF MODELS REPRESENTING CREEP OF ALLOY 617... Key Links Curriculum Vitae 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
