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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!
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Nuclear Science and Engineering
February 2025
Nuclear Technology
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Latest News
INL joins with Idaho universities on advanced projects
New Strategic Understanding for Premier Education and Research (SUPER) agreements signed by Idaho National Laboratory, Boise State University, and the University of Idaho will foster collaboration among the institutions in advanced energy and cybersecurity projects. The five-year agreements are designed to open doors for research and development opportunities, while advancing existing research and development initiatives, including projects in nuclear energy and high-performance computing.
Technical Session|Panel|Sponsored by FCWMD
Monday, November 16, 2020|1:00–3:10PM EST
Session Chair:
Kaushik Banerjee
Session Organizer:
Alternate Chair:
Christina Leggett
Staff Producer:
Eileen Cullen (American Nuclear Society)
Spent nuclear fuel (SNF) cask systems are evaluated for approved contents that provide bounding fuel characteristics (design-basis) such as fuel type, initial enrichment, and discharge burnup. The bounding fuel characteristics establish the upper limits of the cask's safety parameters (e.g., dose rates). Due to the wide variation in SNF assembly burnup values and discharge dates, cask systems are loaded with assemblies that satisfy the bounding fuel characteristics with some amount of uncredited safety margin. In this session, we will discuss (1) design-basis and as-loaded analysis approaches and (2) various applications of uncredited safety margins that can be quantified by as-loaded analyses. The as-loaded analysis approach has the potential to significantly improve SNF management and streamline the regulatory review process.
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