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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.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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Feedback from nuclear sector to inform hearing on NRC licensing process
Leaders of the House Committee on Energy and Commerce last month sent letters to a variety of nuclear sector stakeholders requesting input in preparation for a June 14 hearing titled “Oversight of NRC: Ensuring Efficient and Predictable Nuclear Safety Regulation for a Prosperous America.” (The hearing will be livestreamed at https://energycommerce.house.gov/.)
“We invite you to submit to the committee information and recommendations to improve the licensing review and approval process, as well as the oversight of NRC licensees,” the lawmakers wrote. “We are interested in NRC activities involving the licensing and oversight of today’s operating reactors, as well as the siting, licensing, construction, and oversight of advanced nuclear reactor technologies.” The letter also noted the committee’s interest in “improving NRC efficiency, management of regulatory costs and fees, public health and safety, staff effectiveness and culture, collaboration with the Department of Energy, and international activities.”
Technical Session|Sponsored by RPD
Thursday, December 2, 2021|3:05–4:50PM EST |Fairchild
Zeyun Wu (VCU)
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Verification of Medium-Wise Multi-Group Cross Section Calculation Capability of FRENDY/MG
Go Chiba (Hokkaido Univ.), Akio Yamamoto (Nagoya Univ.)
Reactivity Insertion Transient Analysis for C5G7-TD Benchmark with PANDAS-MOC
Shunjiang Tao (Purdue Univ.), Yunlin Xu (Purdue Univ.)
Bayesian Transposition: A Practical Approach Using Nuclear Reactor Start Up Data
Pamela A. Lopez (CNRS), Adrien Bidaud (CNRS)
Monte Carlo Simulation of Liquid Fuel Flow in Molten Salt Reactor in the iMC Code
HyeonTae Kim (KAIST), Yonghee Kim (KAIST)
Adaptive Mesh Refinement in Monte Carlo Neutron Simulations
Kristin Stolte (Texas A&M Univ.), Pavel Tsvetkov (Texas A&M Univ.)
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