ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
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.