Advanced Materials Program Summary
DOE Office of Nuclear Energy: Strategic Vision
Alloy 709 Code Qualification Status
A “Staged” Qualification Approach for Alloy 709 Code Cases Is Being Executed by the Fast Reactors Campaign
Development of Surveillance Test Articles for Materials Degradation Management in MSR Environment
Information on materials degradations during advanced reactor operations is limited Effects of materials degradations during reactor operations are synergistic, involving: Irradiation, corrosion, elevated temperature exposure and stress (creep-fatigue loading) Establishment of surrogate materials surveillance program for the management of materials degradations would be an important pathway in support of the timely licensing of advanced reactors
Alloy 709 Advanced Austenitic Stainless Steel
History of 20Cr-25Ni Austenitic Alloys
U.S. High Temperature Materials Highlights
U.S. GIF VHTR work is continuing on graphite qualification, Alloy 617 regulatory issues beyond the Code space, Alloy 800H weldments, and ASME Codes and Standards R&D is still considering both pebble bed and prismatic and steam generator and heat exchanger U.S. DOE Advanced Reactor Demonstration Program (ARDP) Two U.S.-based teams were selected to demonstrate advanced […]
An Initial Assessment of the Creep-Rupture Strengths for Weldments with Alloy 800H Base Metal and Alloy 617 Filler Metal
The expected minimum stress-to-rupture of the weld is a function of the stress rupture factor (R) and the expected minimum stress-to-rupture (Sr) of the base metal.
Development of Test Articles for Surrogate Materials Surveillance
Materials Degradation During Advanced Reactor Operations
Integrated FY21 Elevated Temperature Mechanical Testing Results for Alloy 709 Code Case
This report provides the status of creep, fatigue, and creep-fatigue testing that transpired in Fiscal Year 2021 at Argonne National Laboratory, Idaho National Laboratory and Oak Ridge National Laboratory. This testing is being conducted to develop the data package to qualify Alloy 709 in Section III, Division 5 of the American Society of Mechanical Engineers […]
High Temperature Alloys Session 2
Development History of Construction Rules for High Temperature Reactors Components
ART Advanced Materials Program Overview
Design, construction and operation considerations for structural materials.