VERIFICATION OF ALLOWABLE STRESSES IN ASME SECTION 3 SUBSECTION NH FOR GRADE 91 STEEL
American Society of Mechanical Engineers
This document is the outcome derived from an agreement between the U.S. Department of Energy (DOE) and ASME Standards Technology, LLC (ASME ST-LLC) for the Generation IV (Gen IV) Reactor Materials Project. It provides technical information necessary to update and expand appropriate ASME materials, construction and design codes for application in future Gen IV nuclear reactor systems that operate at elevated temperatures, with emphasis on Grade 91 Steel (9Cr-1Mo-V).
| Document Type | Standard |
| Status | Current |
| Publisher | American Society of Mechanical Engineers |
