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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
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June 2025
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Latest News
ANS holds Educator Training webinar on nuclear waste
Loewen
Perfetti
A recent American Nuclear Society webinar tackled misconceptions about nuclear waste. Christopher Perfetti, an associate professor of nuclear engineering at the University of New Mexico, presented “The How, Why, and Where of Nuclear Waste,” the latest online event in ANS’s Educator Training series.
Moderated by ANS past president Eric Loewen (2011–12), this presentation was built to be an accessible and informative Nuclear Waste 101 offering as part of the Society’s broader effort to develop a program specifically tailored to educating K-12 teachers.
Technical Session|New and Advanced Reactors
Monday, August 21, 2023|1:30–3:10PM EDT|Embassy
Session Chair:
Rui Hu
Session Organizer:
Alternate Chair:
Emre Tatli (Westinghouse)
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Post-Test Analysis of SIRIO Facility Data by System Thermal-Hydraulic Codes for LFR Application
1:30–1:50PM EDT
T. Del Moro (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), G. Khalil Youssef (Sapienza Univ. Rome), P. Lorusso (ENEA), M. Caramello (Ansaldo Nucleare), M. Cauzzi (SIET), M. Tarantino (ENEA)
Paper
Presentation Slides (Visible to Attendees)
Experimental Research of the MYRRHA Primary Pump Hydraulic Characteristics at a Reduced Scale
1:50–2:10PM EDT
Mikhail Iarmonov (SCK CEN), Katrien V. Tichelen (SCK CEN)
Asymmetric Decay Heat Removal in MYRRHA: Experiments in the E-SCAPE Facility
2:10–2:30PM EDT
J. Pacio (SCK CEN), R. Serrano Diogo (SCK CEN), K. Van Tichelen (SCK CEN)
Thermal-Hydraulic Analysis of the FFTF LOFWOS Transient with the SPECTRA Code
2:30–2:50PM EDT
F. Alcaro (Nuclear Research & Consultancy Group), M.M. Stempniewicz (Nuclear Research & Consultancy Group)
Presented by Fajar Sri Lestari Pangukir (NRG)
Multiscale Effects in Sodium Fast Reactors: Feedback from the Open Phase of the FFTF LOFWOS-13 Test
2:50–3:10PM EDT
Antoine Gerschenfeld (CEA), Yannick Gorsse (CEA), Simon Li (CEA)
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