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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
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!
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May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NC State releases feasibility study for new research and test reactor
North Carolina State University has completed a feasibility study for its planned advanced research and test reactor. The $3 million study, which was undertaken by the university at the direction of the North Carolina General Assembly, is described in the full report, includes recommendations and projected costs and timelines.
Reactor type: NC State prefers the new reactor to be of “a multipurpose advanced sodium-cooled mixed/coupled spectrum design,” according to the report. Such a design would make the reactor “the only sodium-cooled fast research and test reactor in the country.”
Technical Session|Sponsored by MCD
Wednesday, June 10, 2020|12:00–2:10PM EDT
Alternate Chairs:
Steven P. Hamilton
Madicken Munk (Univ. of Illinois, Urbana-Champaign)
Session Organizer:
Staff Producer:
Rick Michal (American Nuclear Society)
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To access paper attachments, you must be logged in and registered for the meeting.
Assessing the Effectiveness of Acceleration Methods for Deterministic Neutron Transport Solvers
J. S. Rehak (Univ. of California, Berkeley), R. N. Slaybaugh (Univ. of California, Berkeley)
Paper
Stability Analysis of CMFD Acceleration and Linear Prolongation for Weighted Linear Difference Schemes
Rodolfo M. Ferrer (Studsvik Scandpower)
A Hybrid Neutronics Method with Diffusion Synthetic Acceleration for k-eigenvalue Problem
Jiahao Chen (NC State Univ.), Jason Hou (NC State Univ.)
Hybrid Parallel Computing of Solving 3D Multi-group Neutron Diffusion Equation via Multi-level CMFD Acceleration
Shunjiang Tao (Purdue Univ.), Yunlin Xu (Purdue Univ.)
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