ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NWMO chooses vendors for Canadian repository
Canada’s Nuclear Waste Management Organization has selected five companies it is to work with to design and plan the organization’s proposed deep geologic repository for spent nuclear fuel. As the owner of the project, the NWMO will be working with WSP Canada, Peter Kiewit Sons (Kiewit), Hatch Ltd., Thyssen Mining Construction of Canada, and Kinectrics.
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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