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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
April 2025
Nuclear Technology
Fusion Science and Technology
Latest News
$900M offer for SMR funding opens again—realigned to energy dominance agenda
The Department of Energy reissued a $900 million solicitation on March 24 designed to de-risk the deployment of “Gen-III+” light water small modular reactors. The same funding was previously offered in October 2024, with applications due January 17. Now, potential applicants have until April 23 to apply for a grant under a solicitation modified to “better align with President Trump's bold agenda to unleash American energy and AI dominance.”
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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