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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.
Advances in Thermal Hydraulics (ATH 2024)
Technical Session
Wednesday, November 20, 2024|10:00–11:45AM EST|Coral A
Session Chair:
Rui Hu (ANL)
Alternate Chair:
Bart Verdonschot (NRG)
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A Numerical Test Bed on Algorithms Efficient for Advanced System Analysis Code Development
10:00–10:20AM EST
Ling Zou (ANL), Rui Hu (ANL)
Paper
Implementing a Corrosion-Oxidation Modeling Capability in SAM for Lead-Cooled Fast Reactors
10:20–10:40AM EST
Travis Mui (ANL), Thanh Hua (ANL), Ling Zou (ANL), Rui Hu (ANL), Jun Liao (Westinghouse Electric Co.)
Severe Accident Analysis of OPR-1000 Plant Using CINEMA Code
10:40–11:00AM EST
Jun-young Kang (KAERI), Donggun Son (KAERI), Jae Hyun Ham (KAERI), Yong Mann Song (KAERI), Jun Ho Bae (KAERI)
A New One-Dimensional Model for Thermal Mixing and Stratification in Reactor Applications
11:00–11:20AM EST
Eric Cervi (ANL), Ling Zou (ANL), Yeongshin Jeong (ANL), Rui Hu (ANL)
Development of A System Analysis Model to Evaluate the Conceptual Design of the Reactor Cavity Cooling System of the Horizontal Compact High Temperature Gas-Cooled Reactor (HC-HTGR)
11:20–11:40AM EST
Yeongshin Jeong (ANL), Darius Lisowski (ANL), Qiuping Lv (ANL), Rui Hu (ANL)
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