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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
FERC denies Talen -Amazon agreement—again
The Federal Energy Regulatory Commission has doubled down on its rejection of an interconnection service agreement (ISA) between Amazon Web Services and Talen Energy in Pennsylvania.
Advances in Thermal Hydraulics (ATH 2024)
Technical Session
Wednesday, November 20, 2024|8:00–9:45AM EST|Coral C
Session Chair:
Robert Kile (INL)
Alternate Chair:
Dezhi Dai (ANL)
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Assessment of Intermediate Break Loss of Coolant Accident with TRACE code
8:00–8:20AM EST
Seung Hun Yoo (Korea Institute of Nuclear Safety), Yong Seok Choi (Korea Institute of Nuclear Safety), Sungchu Song (Korea Institute of Nuclear Safety)
Paper
Code Benchmark of a Depressurized Conduction Cooldown Transient in the High Temperature Test Facility
8:20–8:40AM EST
Robert F. Kile (INL), Aaron S. Epiney (INL), Thanh Hua (ANL), Ling Zou (ANL), Sung Nam Lee (KAERI), Geoff Waddington (Canadian Nuclear Laboratories), Xianmin Huang (Canadian Nuclear Laboratories), Tariq Jafri (Canadian Nuclear Laboratires), Fajar Pangukir (Nuclear Research and Consultancy Group), Marek Stempniewicz (Nuclear Research and Consultancy Group), Ferry Roelofs (Nuclear Research and Consultancy Group), Gustáv Mayer (HUN-REN Centre for Energy Research), Zsombor Bali (HUN-REN Centre for Energy Research)
Bond Graph Modeling Based System Scaling Analysis: Quantifying the Impact of Distortions
8:40–9:00AM EST
Marcos G. Ortiz (Information Systems Laboratories)
Progress Towards the Lower Plenum Mixing Test of the High Temperature Test Facility Benchmark by NRG and OSU
9:00–9:20AM EST
M.M.M.D. Hussain (NRG), B. Nakhnikian-Weintraub (OSU), I. Gutowska (OSU)
A Cross-Code Verification Study for Conjugate Heat Transfer in Gas-Cooled Pebble Bed Reactors
9:20–9:40AM EST
Dezhi Dai (ANL), Haomin Yuan (ANL), Prasad Vegendla (ANL), Adrian Tentner (ANL), John Acierno (Penn State), Michael Seneca (Penn State), Tri Nguyen (Penn State), Elia Merzari (Penn State)
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