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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
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.
Technical Session|New and Advanced Reactors
Tuesday, August 22, 2023|10:45AM–12:25PM EDT|Columbia 2
Session Chair:
Mauricio Tano (INL)
Alternate Chair:
Lambert Fick (Kairos)
Session Organizer:
Rui Hu
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Design and Construction of an Integral-Effect Test Facility FLUSTFA for Molten Salt Reactor Applications
10:45–11:05AM EDT
Sheng Zhang (Univ. Michigan), Hsun-Chia Lin (Univ. Michigan), Minghui Chen (Univ. Michigan), Shanbin Shi (Univ. Michigan), Shuai Che (Univ. Michigan), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Qiuping Lv (ANL)
Paper
Initial Operation of a High-Temperature Fluoride Salt Test Facility (FLUSTFA): Issues Identified and Paths Forward
11:05–11:25AM EDT
Sheng Zhang (Univ. Michigan), Shuai Che (Univ. Michigan), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan)
Design of a Natural Circulation Experiment to Investigate Flow Stability
11:25–11:45AM EDT
J.S. Narvaez Arrua (Univ. Grenoble Alpes), P. Rubiolo (Univ. Grenoble Alpes), J. Giraud (Univ. Grenoble Alpes), V. Ghetta (Univ. Grenoble Alpes), A. Cammi (Politecnico di Milano), S. Lorenzi (Politecnico di Milano)
Flow-Informed Corrosion in Molten Salts Using the Poisson-Nernst-Planck Model
11:45AM–12:05PM EDT
M. Tano (INL), S. Walker (INL), A. Abou-Jaoude (INL)
Fuel Flow Modeling Under Thermal Fluidics Considerations Within Operational Domains of Molten Salt Reactors
12:05–12:25PM EDT
Thabit M. Abuqudaira (TAMU), Pavel V. Tsvetkov (TAMU), Piyush Sabharwall (INL)
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