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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Nov 2024
Jul 2024
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Technical Session|Sponsored by THD
Friday, December 3, 2021|1:00–2:45PM EST |Columbia 11
Session Chair:
Bob Martin
Alternate Chair:
Arturo Cabral
Session Organizer:
Lander Ibarra
Student Assistant:
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SAM Code Validation of Natural Convection in Molten Salt
1:05–1:25PM EST
Jadyn Reis (Texas A&M Univ.), Michael Gorman (Texas A&M Univ.), Brent Hollrah (Texas A&M Univ.), Rodolfo Vaghetto (Texas A&M Univ.), Yassin Hassan (Texas A&M Univ.)
Paper
Validation Effort for the OSU HTTF PG-28 Test Using RELAP5-3D
1:25–1:45PM EST
Joshua K. Halsted (Oregon State Univ.), Izabela Gutowska (Oregon State Univ.)
Preliminary Analysis of Journal Bearings for Molten Salt Pumps
1:45–2:05PM EST
Yuqi Liu (Univ. of New Mexico), Minghui Chen (Univ. of New Mexico)
Preliminary Thermal-Hydraulic Analysis for Heat Pipe Irradiation Test in the MIT Reactor
2:05–2:25PM EST
Aaron S. Epiney (INL), David M. Carpenter (MIT), Justin Johnson (INL)
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