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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
September 2025
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August 2025
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Latest News
The RAIN scale: A good intention that falls short
Radiation protection specialists agree that clear communication of radiation risks remains a vexing challenge that cannot be solved solely by finding new ways to convey technical information.
Earlier this year, an article in Nuclear News described a new radiation risk communication tool, known as the Radiation Index, or, RAIN (“Let it RAIN: A new approach to radiation communication,” NN, Jan. 2025, p. 36). The authors of the article created the RAIN scale to improve radiation risk communication to the general public who are not well-versed in important aspects of radiation exposures, including radiation dose quantities, units, and values; associated health consequences; and the benefits derived from radiation exposures.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|1:00–2:45PM PDT|Redondo
Session Chair:
Subash Sharma (UMass Lowell)
Alternate Chair:
Trevor Howard (Oregon State)
Session Organizers:
Matthew D. Zimmer (Naval Nuclear Lab)
Xu Wu (NCSU)
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CFD Analysis of the Sodium-Water Reaction in the Minichannel of PCSG Designed for SFR
Taewoo Kim (Korea Univ. Science and Technology), Hyun-Sik Park (KAERI), Sang Ji Kim (KAERI)
Paper
A Multiphysics Framework Using High Resolution DNS to Optimize Conditions for Plasma Formation
Naveen Pillai (NCSU), Nicholas L. Sponsel (NCSU), Katharina Stapelmann (NCSU), Igor A. Bolotnov (NCSU)
A Conceptual Study of Air Curtain on the Reactor Vessel Auxiliary Cooling System
Jaejin Choi (KAIST), Yong Hoon Jeong (KAIST)
Development of Integrated Safety Analysis Code with Capability of Detailed Simulation for Multiple Fuel Rods
Yunseok Lee (Incheon National Univ.), Jaeseung Suh (SenTech Co.), Taewan Kim (Incheon National Univ.)
LES of Natural Convection Along the Vertical Wall Applied for the Scale of Small Modular Reactor ( Ra*≈10^19)
Songzhi Yang (CEA), Ulrich Bieder (CEA)
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