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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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June 2025
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Latest News
ANS holds Educator Training webinar on nuclear waste
Loewen
Perfetti
A recent American Nuclear Society webinar tackled misconceptions about nuclear waste. Christopher Perfetti, an associate professor of nuclear engineering at the University of New Mexico, presented “The How, Why, and Where of Nuclear Waste,” the latest online event in ANS’s Educator Training series.
Moderated by ANS past president Eric Loewen (2011–12), this presentation was built to be an accessible and informative Nuclear Waste 101 offering as part of the Society’s broader effort to develop a program specifically tailored to educating K-12 teachers.
Technical Session|Verification, Validation and Uncertainty Quantification
Wednesday, August 23, 2023|1:30–3:10PM EDT|Embassy
Session Chair:
Lucia Rueda (ENGIE)
Alternate Chair:
Xingang Zhao (ORNL)
Session Organizer:
Joshua Kaizer
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Uncertainty Quantitative Analysis on Sub-channel Code by MCMC Algorithm Based on Bayesian Principle
1:30–1:50PM EDT
Xin He (Shanghai Jiao Tong Univ.), Meiqi Song (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.)
Paper
Attachment
Presentation Video (Visible to Attendees)
BWR Core Thermal-Hydraulic Uncertainty and Sensitivity Analysis with Improved Bypass Modeling Features
1:50–2:10PM EDT
Devshibhai Ziyad (NCSU), Agustin Abarca (NCSU), Maria Avramova (NCSU)
Assessment of Subchannel Analysis Capability of Thermal-Hydraulic System Codes for Detailed Fuel Bundle Simulation
2:10–2:30PM EDT
Yunseok Lee (Incheon Nat'l Univ.), Taewan Kim (Incheon Nat'l Univ.)
Numerical Investigation of Thermal-Hydraulic Behavior During the Reflood Phase Using COSINE Subchannel Code
2:30–2:50PM EDT
Lin Chen (Shanghai Jiao Tong Univ.), Hao Zhang (Shanghai Jiao Tong Univ.), Lixin Du (Shanghai Jiao Tong Univ.), Yingran Guo (Shanghai Jiao Tong Univ.), Yanhua Yang (Shanghai Jiao Tong Univ.), Meng Zhao (Shanghai Jiao Tong Univ.), Yixuan Cheng (Shanghai Jiao Tong Univ.), Zhi Yang (Shanghai Jiao Tong Univ.)
Reflood Experimental Verification and Grid Sensitivity Analysis for COSINE Subchannel Code Based on Two-Fluid Eight Equations
2:50–3:10PM EDT
Yixuan Cheng (Shanghai Jiao Tong Univ.), Lin Chen (Shanghai Jiao Tong Univ.), Hao Zhang (Shanghai Jiao Tong Univ.), Meng Zhao (Shanghai Jiao Tong Univ.), Yanhua Yang (Shanghai Jiao Tong Univ.)
Presentation Video (Visible to Attendees) — NURETH20_40708
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