Design by analysis rules for ASME Section III, Division 5, Class B components
The current rules for elevated temperature ASME Section III, Division 5, Class B components, other than piping, were basically adapted from the Design-by-Rule approach for Section VIII, Division 1 vessels. A goal of the proposed new rules is to explicitly account for the design life and cyclic service while recognizing the less-rigorous requirements commensurate with […]
Fast Reactor Materials R&D Update
Presentation detailing Major focus: Deployment of A709 for fast reactor structural applications in the area of Design, Fabrication, Supply Chain, and Adx Rx Operation. Also discuss additional work to support A709 development, High level timeline for Irradiation design data, and processing parameters.
High Temperature Materials Program Overview
The ART advanced materials program focuses on the application of materials and design methods to support advanced reactors deployment in the near and mid-term Covering materials, design, construction, licensing and operations. These slides speak to present and future Materials focus.
ART Advanced Materials Overview
The ART advanced materials program focuses on the application of materials and design methods to support advanced reactors deployment in the near and mid-term. This covers materials, design, construction, licensing and operations.
A709 Code Case Design Parameters
Joint ART Materials/AMMT Program Review to be given at DOE Headquarters on June 5-8, 2023. A709 Code Case Design Parameters regarding preliminary efforts have been started to develop design parameters from test data. Thus far, most of the data evaluated were from the first two commercial heats. Data from these commercial heats continue to support […]
Materials Surveillance Development
This presentation is to update DOE at the Molten Salt Program review in May on the work at INL and Argonne National Laboratory on surveillance specimen development. This includes thermal-mechanical testing and test article designs.
Experimental and Analytical Verification of ASME Section IiII Division 5 Creep-Fatigue Design Rules
The continuous advancement of structural materials and the growing demands for more reliable and economical structural components in high-temperature reactor applications have necessitated the development of comprehensive design methodologies and design rules. Mechanical degradation of structural components at elevated temperatures subjected to cyclic deformation is controlled by the creep-fatigue damage. Over the past few decades, […]
A summary of the mechanical properties data developed in FY 2023 by ANL, INL and ORNL to support the data package development for the A709 Code Case
This report provides the status of tensile, creep, fatigue, and creep-fatigue testing to date conducted at Argonne National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory to generate the data package required to qualify Alloy 709 in American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Division 5. The Division 5 […]
Machining of Alloy 709 Creep-fatigue Specimens from G. O. Carlson Heat
Alloy 709 has been selected as the next candidate material for Section III, Division 5 qualification in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) for elevated-temperature nuclear construction. The qualification data package requires an assortment of information and material data including tensile, creep, and creep-fatigue performance at elevated temperatures […]
ASME Section III, Division 5, High Temperature Reactors
Section III, Division 5 stands ready to support near-term deployment of advanced reactors. Progress on improving design rules, extending design lifetimes, adding more materials, and adding advanced component fabrication methods. Lessons-learned from Alloy 617 Code Case effort have streamlined the balloting workflow for Class A material code cases. After requester submitted material design parameters and […]