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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Finland’s Onkalo repository licensing gets stuck again
Finland’s regulatory authority, the Radiation and Nuclear Safety Authority (STUK), announced that it was further delaying issuing a statement on the safety case for the Onkalo spent nuclear fuel repository until 2025, saying that Posiva’s license application material is not yet ready.
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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