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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
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
Technical Session|Sponsored by THD
Wednesday, December 1, 2021|2:35–4:00PM EST |Columbia 10
Session Chair:
Subash Sharma
Alternate Chair:
Tri Nguyen
Session Organizer:
Jun Fang
Student Assistant:
Gavin VanderBroeder
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A New Two Fluid Model Verification Problem
2:40–3:00PM EST
Raghav Ram (Purdue Univ.), Krishna Chetty (Advanced Cooling Technologies), Alejandro Clausse (CNEA-CONICET), Martin Lopez-de-Bertodano (Purdue Univ.)
Paper
Development of Computational Models for Molten Salt Reactor (MSR) Using MOOSE Code
3:00–3:20PM EST
Anthony G. Bowers Jr. (Univ. of Massachusetts, Lowell), Subash L. Sharma (Univ. of Massachusetts, Lowell)
Attachment
Recalibration in the Fully Turbulent Regime of the UCTD Correlation for the Friction Factor in Wire-Wrapped Rod Bundles Using Multi-Objective Genetic Algorithms
3:20–3:40PM EST
Gabriel C.Q. Tomaz (Texas A&M Univ.), Y.M. Chen (Texas A&M Univ.), Rodolfo Vaghetto (Texas A&M Univ.), Yassin Hassan (Texas A&M Univ.)
Development of Modeling Techniques for a Reactor Core Cooling System Facility with TRACE
3:40–4:00PM EST
Alessandro Vanni (TAMU), Rodolfo Vaghetto (TAMU), Yassin A. Hassan (TAMU)
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