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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
Technical Session|Sponsored by THD
Wednesday, November 18, 2020|12:00–2:10PM EST
Session Chair:
Dillon R. Shaver
Alternate Chair:
Elia Merzari (Penn State)
Session Organizer:
Igor A. Bolotnov (NCSU)
Staff Producer:
Erica McGowan (American Nuclear Society)
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Verification of Transient Simulations Using the SAS4A/SASSYS-1 Coupled Channel Interface
Daniel O'Grady (Argonne National Laboratory), Guanheng Zhang (Argonne National Laboratory), Thomas H. Fanning (Argonne National Laboratory), Rui Hu (Argonne National Laboratory), Guojun Hu (Argonne National Laboratory), Thanh Q. Hua (Argonne National Laboratory), Acacia J. Brunett (Argonne National Laboratory)
Paper
Joint SAS4A/SASSYS-1 Development for Lead Cooled Fast Reactor Safety Analysis
Anton Moisseytsev (ANL), Thomas H. Fanning (ANL), Daniel O’Grady (ANL), Thanh Quoc Hua (ANL), Adrian M. Tentner (ANL), Aydin Karahan (ANL), Acacia J. Brunett (ANL), Tanju Sofu (ANL), Michael Epstein (Fauske & Associates, LLC), Sung Jin Lee (Fauske & Associates, LLC), Daniel L. Wise (Westinghouse Electric Co.), Paolo Ferroni (Westinghouse Electric Co.), Jun Liao (Westinghouse Electric Company)
Implementation of an Extended Reactor Vessel Heat Rejection Modeling Capability in SAS4A/SASSYS-1
Thomas H. Fanning (Argonne National Laboratory), Acacia J. Brunett (Argonne National Laboratory), Daniel O'Grady (Argonne National Laboratory)
NekRS: Massively parallel fluid flow simulations in reactor cores
Elia Merzari (Pennsylvania State University), Misun Min (Argonne National Laboratory), Yu-Hsiang Lan (Argonne National Laboratory), Stefan Kerkemeier (Argonne National Laboratory), Paul Fischer (University of Illinois)
Statistical Uncertainties of Passive Scalars in a Direct Numerical Simulation of Low-Prandtl Fluid Flow over a Backward Facing Step
Iztok Tiselj (Jožef Stefan Institute), Jure Oder (Jozef Stefan Institut)
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