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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Edward L. Quinn (Technology Resources), Wayne Marquino (Ge Hitachi Nuclear Energy), Ron Jarrett (TVA), Kirklyn Melson (EXCEL Services Corp.), David Rahn (NRC)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1336-1345
The purpose of this paper is to provide an overview of the update to International Society of Automation (ISA) Standard ISA S67.04 – 2006, “Setpoints for Nuclear Safety-Related Instrumentation for Nuclear Power Plants,” (Reference 1) and ISA RP 67.04-2000, “Methodologies for Determination of Setpoints for Nuclear Safety-Related Instrumentation” (Reference 2). Significant advances have occurred on the utility, Nuclear Steam Supply System (NSSS) vendor, and regulatory side, related to improved techniques for analysis and monitoring. These and other changes, including those related to Technical Specifications and surveillance interval extensions, are being included in the latest update to this primary standard for setpoint control in nuclear plants in the U.S. and around the world. In 2016, the ISA S67.04 Committee agreed to proceed with a revision to this Standard and Recommended Practice, with major updates in the following areas: 1. Definitions – Updates for improved definitions based on TSTF-493, Rev 4 (Reference 3), RIS-2006-17 (Reference 4) and NRC draft Regulatory Guide (RG) 1.105 (Reference 10) 2. 95/95 – Updates based on improved guidance on the development of component input data and analysis techniques for 95% probability/95% confidence calculations 3. TSTF-493, RIS 2006-17 updates for Technical Specification input and to support changes 4. NRC input in the draft Regulatory Guide 1.105 (Reference 10) and the Branch Technical Position BTP-7-12 (Reference 6) revision process. 5. Improved guidance from the Electric Power Research Institute (EPRI) in References 7, 8 and 9. These standards are being updated with a new version to be issued for ISA approval in 2018.
