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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Ken Muramatsu, Kunihisa Soda
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 907-911
Technical Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27684
Articles are hosted by Taylor and Francis Online.
The hydrogen burn that occurred in the Three Mile Island Unit 2 (TMI-2) accident raised a concern on the possible threat to the containment integrity of a light water reactor during a severe accident, and a great deal of analytical and experimental studies were conducted after the accident. To properly assess the hydrogen behavior in the TMI-2 accident, thermal-hydraulic response in the containment needs to be adequately described. The purpose of the present study was to estimate the thermal-hydraulic response during the hydrogen burn in the TMI-2 accident by using the CONTAIN1.1 code. It was concluded from the present analysis that the hydrogen behavior was reasonably well predicted by using CONTAIN1.1 with adequately selected set of parameters in the hydrogen burn model.