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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand Resort
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
Sep 2022
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
October 2022
Nuclear Technology
Fusion Science and Technology
Latest News
OPG, Microsoft to work toward net-zero future for Ontario
Ontario Power Generation and Microsoft Canada have formed a partnership aimed at combatting climate change and driving sustainable growth across the province of Ontario, the Canadian utility announced this week.
Under the partnership, Microsoft will procure clean energy credits (CECs) sourced from OPG’s nuclear and hydro assets in Ontario on an hourly basis. (OPG’s nuclear assets include the four-unit Darlington plant and six-unit Pickering facility.) According to the announcement, this will enable Microsoft to advance toward its 100/100/0 by 2030 goal, which commits the software firm to powering its data centers globally with zero-carbon energy, 24/7.
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)
Summary
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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