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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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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.
Sidney Langer
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 294-297
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27656
Articles are hosted by Taylor and Francis Online.
The tacit assumption in early severe accident studies was that the melting of a reactor core would result in failure of the reactor pressure vessel and eventual failure of the containment building and release of fission products to the environment. This assumption was shown to be wrong by the Three Mile Island Unit 2 (TMI-2) accident in which 50% of the core melted, yet fission product release to the environment was insignificant (<5% of the noble gases). Termination of the accident and survival of the reactor vessel is attributed to the presence of water in the vessel. The quantity of water required to cool the molten core and reestablish stable core cooling is calculated. These calculations and the TMI-2 experience imply that future accident management strategies that emphasize restoration of the cooling water supply can terminate advanced severe accidents and avoid pressure vessel failure.