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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.
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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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BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
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.