• General Corrosion
    • Wastage
    • Flow Accelerated Corrosion (FAC)
    • Fouling
  • Wear
  • Stress Corrosion Cracking
    • IGSCC/TGSCC
    • IASCC
    • ODSCC
    • IDSCC/PWSCC
  • Fatigue
    • High Cycle Fatigue
    • Low Cycle Fatigue
    • Environmental Fatigue
  • Fracture
    • Thermal Aging Embrittlement
    • Reduction in Fracture Properties
  • Irradiation Effects
    • Irradiation Embrittlement
    • Void Swelling
    • Irradiation Creep/Stress Relaxation
  • Microstructure/RIS
Updating...
id title access pubDate type
  • 3002034662 Steam Generator Management Program: Inhibitor to Lead-Induced Stress Corrosion Cracking of Steam Generator Tubing Member/
    Funder     2026-03-13 TECHNICAL REPORT
    i
  • 3002032196 Materials Reliability Program Seismic Fatigue Research Compendium (MRP-500): A State-of-the-Art Compilation of Seismic Research Relevant to Commercial Nuclear Components Public 2025-12-23 TECHNICAL UPDATE
    i
  • 3002029396 Materials Reliability Program: Strategic Management of Unmitigated PWR Alloy 82/182 Piping Butt Welds Operating at Reactor Cold Leg Temperature (MRP-493) Member/
    Funder     2025-12-19 TECHNICAL REPORT
    i
  • 3002032190 EPRI Environmentally Assisted Fatigue (EAF) Component Test-Refined Component Modeling Analysis Based on Benchmark Test Data: Results from Initial Benchmark Data Collection Member/
    Funder     2025-12-18 TECHNICAL UPDATE
    i
  • 3002032197 Materials Reliability Program: Hot Cell Examination and Testing of U.S. PWR Core Barrel Specimens (MRP-497) Member/
    Funder     2025-12-16 TECHNICAL REPORT
    i
  • 3002032187 MRP Database Web Application v1.0 Member/
    Funder     2025-12-16 SOFTWARE
    i
  • 3002032171 BWRVIP-138, Revision 2-A: BWR Vessel and Internals Project, Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines Member/
    Funder     2025-11-26 TECHNICAL REPORT
    i
  • 3002029403 Materials Reliability Program: Technical Basis of 100°F/hr Heatup and Cooldown Rates in Reactor Pressure Vessel Pressure-Temperature Limit Curves (MRP-490): ASME Section XI Appendix G Public 2025-10-15 TECHNICAL REPORT
    i
  • 3002032352 BWRVIP-100, Revision 2-A: BWR Vessel and Internals Project: Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components Member/
    Funder     2025-10-10 TECHNICAL REPORT
    i
  • 3002033639 Evaluation of Gas Metal Arc-Direct Energy Deposition Type 316LSi Stainless Steel Valve Bodies: Microstructure, Mechanical Properties, Examination, and Aging-Related Testing Public 2025-10-10 TECHNICAL REPORT
    i

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