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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Christopher Poresky, James Kendrick, Per F. Peterson (Univ of California, Berkeley), Roger Lew (Univ of Idaho), Thomas Ulrich, Ronald L. Boring (INL)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 522-535
The Thermal Hydraulics Laboratory in the Nuclear Engineering Department at the University of California, Berkeley constructed the Advanced Reactor Control and Operations (ARCO) facility in January 2018 to serve as an advanced reactor control room and operator support system test bed. ARCO is the control room for the Compact Integral Effects Test (CIET) facility that replicates primary-side flow paths and thermal hydraulic behavior of a Fluoride-salt-cooled High-temperature Reactor (FHR) using simulant fluids and scaling principles. ARCO and CIET together affords experimental operating scenarios for control strategy and user interface iterative design and evaluation for FHRs and, more generally, for advanced small modular nuclear reactor designs. Operating scenarios of primary importance for new reactor designs include rapid load-following, startup and shutdown, and multi-module operation. In addition, ARCO supports research and development of specific and new capabilities for nuclear plant control rooms. Specifically, these capabilities consist of new digital communication tools for operators, sophisticated and intuitive means of on-line data analysis, model-based fault detection for online health monitoring and prognostics, and control room cybersecurity strategies. In short, ARCO is a prototypical control system enhanced with operator support capabilities for advanced small modular nuclear reactors. This paper describes the design basis for ARCO and the forthcoming operator support systems operating alongside the CIET facility.