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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.