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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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|Severe Accidents
Tuesday, August 22, 2023|3:30–5:10PM EDT|Fairchild East/West
Session Chair:
Mitchell T. Farmer
Alternate Chair:
Marco Pellegrini
Session Organizer:
David L. Luxat
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Determination of Effective Heat Transfer Coefficients Using the Decomposition Parameters of Silicate Concrete, the Melt Composition, and the Heating Power with AC²-COCOSYS
3:30–3:50PM EDT
Maximilian Hoffmann (Ruhr Univ. Bochum), Marco K. Koch (Ruhr Univ. Bochum)
Paper
The Role of Zr-Oxidation During Molten Core-Concrete Interaction
3:50–4:10PM EDT
Xiaoyang Gaus-Liu (Karlsruhe Institute of Technology)
Mesh Sensitivity Analysis of the CFD Model of the Core Catcher of the ALLEGRO Reactor
4:10–4:30PM EDT
Jan Komrska (Czech Technical Univ. Prague), Pavel Zacha (Czech Technical Univ. Prague), Petr Vacha (UJV Rez)
Steam Explosion Retardant for Long-Term Coolability
4:30–4:50PM EDT
Masahiro Furuya (Waseda Univ.), Takahiro Arai (CRIEPI)
Thermodynamic Calculation Methodology of Specifically Designed Sacrificial Material for Ex-Vessel Core Catcher
4:50–5:10PM EDT
Erhui Chen (China Nuclear Power Engineering Co.), Li Zhang (China Nuclear Power Engineering Co.), Nan Li (China Nuclear Power Engineering Co.), Xiao Zeng (China Nuclear Power Engineering Co.), Qiang Guo (China Nuclear Power Engineering Co.), Yidan Yuan (China Nuclear Power Engineering Co.), Xiao-Gang Lu (Shanghai Univ.), Yeqing Ding (Shanghai Univ.)
Presentation Video (Visible to Attendees)
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