ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Science and Engineering
April 2025
Nuclear Technology
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Latest News
West Valley shares 3D model and lessons learned
A virtual meeting between representatives of the West Valley Demonstration Project (WVDP) in New York and the Oak Ridge Office of Environmental Management (OREM) in Tennessee was held recently to share lessons learned from the ongoing demolition of West Valley’s main plant process building.
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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