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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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The when, where, why, and how of RIPB design
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series.
Watch the full webinar here.
Technical Session|Advanced Reactor Design and Analysis
Wednesday, April 30, 2025|1:00–2:40PM MDT|E.P. Ensley B
Session Chair:
Vincent Laboure (BWX Technologies)
Alternate Chair:
Yaqi Wang (INL)
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Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design
1:00–1:25PM MDT
Christian Vita (Politecnico di Torino), Nicolo' Abrate (Politecnico di Torino), Sandra Dulla (Politecnico di Torino), Fausto Franceschini (Westinghouse Electric Co.)
Paper
Application of Nodal Numerical Adjoints for Kinetic Parameters Assessment in Two-Step Nodal Code KANT
1:25–1:50PM MDT
Taesuk Oh (KAIST), Dongju Choi (KAIST), Yonghee Kim (KAIST)
LDR Lite Benchmark Core Analysis Exercise with CASMO5 and SIMULATE5
1:50–2:15PM MDT
Emiliya L. Georgieva (Studsvik), Tamer Bahadir (Studsvik)
Mini-Reactor Once-Through Operation Cycle High-Burnup Fuel Depletion Performance Impacts Verification
2:15–2:40PM MDT
Gray S. Chang (JFoster & Assoc.), John D. Bess (JFoster & Assoc.), Patrick Moo (JFoster & Assoc.), Julie Foster (JFoster & Assoc.)
Presentation Slides (Visible to Attendees)
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