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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
Jan 2025
Jul 2024
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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Daisuke Taniguchi, Yuki Ishiwatari, Naoki Hirokawa, Bumpei Fujioka (Hitachi-GE Nuclear Energy)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 494-502
Spent Fuel Storage Pool (SFP) Probabilistic Safety Assessment/Analyses (PSA) is one of the remarkable areas after the Fukushima Dai-ichi accident. Hitachi-GE developed a SFP PSA model for UK ABWR (United Kingdom Advanced Boiling Water Reactor) GDA (Generic Design Assessment) which considered the following characteristics.
? Adverse effects from reactor accident progression
? Structural integrity in case of cask drop onto SFP
? Hydrogen management in the Level 2 PSA modeling
? Seismic
? Internal Fire and Internal Flooding