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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island 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!
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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Water-Cooled Reactor Operations and Accident Analysis
Wednesday, August 23, 2023|3:30–5:10PM EDT|Embassy
Session Chair:
Chul-Hwa Song (KAERI)
Alternate Chair:
Subash Sharma (UM Lowell)
Session Organizer:
Cesare Frepoli
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NRC's Methodology to Estimate Fuel Dispersal During a Large Break Loss of Coolant Accident
3:30–3:50PM EDT
Andrew Bielen (U.S. Nuclear Regulatory Commission), James Corson (U.S. Nuclear Regulatory Commission), Joseph Staudenmeier (U.S. Nuclear Regulatory Commission)
Paper
Methodology and Analysis to Demonstrate Avoidance of Dispersal During a LOCA in Ringhals PWRs
3:50–4:10PM EDT
J. Holmström (Ringhals), M. Holmgren (Ringhals), M. Söderström (Vattenfall Nuclear Fuel), P. Gabrielsson (Vattenfall Nuclear Fuel), A. Surén (Vattenfall Nuclear Fuel)
Reactivity-Initiated Accident Analysis of a High Burnup PWR with a 24-Month Fuel Cycle
4:10–4:30PM EDT
Mason Fox (Univ. Tennessee, Knoxville), Nicholas Brown (Univ. Tennessee, Knoxville), Jianwei Hu (ORNL), Ugur Mertyurek (ORNL)
Presentation Slides (Visible to Attendees)
Evaluation of High-Burnup Fuel Coolability During a Control Rod Withdrawal
4:30–4:50PM EDT
Isabelle Lindsay (Univ. Tennessee, Knoxville), Mason Fox (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville), Nathan Capps (ORNL)
CIFF: Analysis Model of Fuel Failure Risks Caused by CRUD Deposition
4:50–5:10PM EDT
Shiwei Wang (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Hui He (Shanghai Jiao Tong Univ.)
Presentation Video (Visible to Attendees) — pre-recorded presentation video
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