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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
NRC discontinues spent fuel pool rulemaking
The Nuclear Regulatory Commission is discontinuing its rulemaking activity, “Long-Term and Unattended Water Makeup of Spent Fuel Pools,” and denying a petition for rulemaking. The new rule, as requested by the petitioner, would have required nuclear power plant licensees to ensure that their spent nuclear fuel pools are capable of cooling and maintaining water levels during extended power outages.
Workshop
Thursday, April 13, 2023|8:30–11:30AM EDT|Hiwassee
This event is presented by the IAEA.
Hosted by MIT and Argonne National Laboratory
A central problem in nuclear engineering is the simulation of the transit of neutron and photon radiation through devices. Several programs have been written over the past few decades to solve this problem in a generalized fashion via the Monte Carlo method, but only one is not centralized and allows anyone to hack the code and distribute it to others: OpenMC.
For this reason, OpenMC is excellent for students. We'll give an overview of getting OpenMC running on your computer, creating input to the program, and analyzing the results. Particularly, we'll look at a reactor criticality problem and a photon shielding problem, and how OpenMC's python interface enables streamlined analysis compared to older Monte Carlo codes.
Location: Hiwassee
Cost: $0
Attendees: 40
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