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
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Technical Session
Wednesday, May 18, 2022|1:30–3:15PM EDT|Fountainview
Session Chair:
Joshua Hykes (Studsvik Scandpower)
Alternate Chair:
Kimihiro Yokoi (Hitachi-GE Nuclear Energy)
Session Organizer:
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Multiscale Thermal Hydraulic Coupling Methods for Boiling Water Reactor Simulation
Aaron Graham (ORNL), Benjamin Collins (ORNL), Bob Salko (ORNL), Mehdi Asgari (ORNL)
Paper
VERA BWR Progression Problems
Chase Lawing (NCSU), Scott Palmtag (NCSU), Mehdi Asgari (ORNL)
Preliminary Simulation Results of Peach Bottom Unit 2 Cycles 1 and 2 with MPACT
Sooyoung Choi (Univ. Michigan), Andrew Ward (Univ. Michigan), Aaron Graham (ORNL), Benjamin Collins (ORNL), Brendan Kochunas (Univ. Michigan), Mehdi Asgari (ORNL)
Applicability of Neutronics Design Calculation Method for Axially Heterogeneous Core of RBWR (Resource-Renewable Boiling Water Reactor)
Kimihiro Yokoi (Hitachi-GE Nuclear Energy), Tetsushi Hino (Hitachi-GE Nuclear Energy), Kazuya Ishii (Hitachi-GE Nuclear Energy), Junichi Miwa (Hitachi-GE Nuclear Energy), Hideo Soneda (Hitachi-GE Nuclear Energy), Mikolaj Adam Kowalski (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge), Brendan Kochunas (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Yuxuan Liu (Univ. Michigan), Yasunobu Nagaya (Japan Atomic Energy Agency)
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