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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
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).
Technical Session|Sponsored by NCSD
Thursday, June 11, 2020|12:15–2:00PM EDT
Session Chair:
Kristin N. Smith
Alternate Chair:
Travis M. Greene
Session Organizer:
Vladimir Sobes
Staff Producers:
Patricia Schroeder (American Nuclear Society)
Kathryn Murdoch (American Nuclear Society)
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Description and Use of SCALE Sampler Parametric Capability for Engineering Analysis and Optimization
W. J. Marshall (ORNL), T. M. Greene (ORNL), B. D. Brickner (ORNL), R. A. Hall (ORNL)
Paper
Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Applicable Experiment Selection
W. J. Marshall (ORNL), J. B. Clarity (ORNL), K. Banerjee (ORNL)
Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Sensitivity Calculations
Criticality Safety Analysis of Fresh Fuel Storage of Barakah Nuclear Power Plant
Shaikha A. AlShamsi (Univ. of Sharjah), Walid A. Metwally (Univ. of Sharjah), Batool M. Madani (Univ. of Sharjah)
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