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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Özlem Yilmaz, Michael Buck, Jöoerg Starflinger (Univ of Stuttgart)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 900-909
In case of a severe accident in a light water reactor, core melt can be released from the reactor pressure vessel and dislocate to the reactor cavity where it attacks the concrete structures. In order to avoid possible containment failure due to molten corium concrete interaction, the molten corium is to be retained and cooled. Core-catcher concepts considering water-injection via the bottom into the melt layer can lead to rapid quenching and solidification of the melt layer, forming a highly porous structure. The COMET-PC concept relies on porous concrete layers to distribute the water below the melt layer. This paper presents investigations on hydraulics of prototypical porous concretes that have been being used for the experimental verification of the COMET-PC core-catcher system. Pressure losses within these concretes were measured for various water flow rates to determine permeability and passability of the porous concretes. Measurement results were applied in simulations of COMET-PC experiments and reactor application with the COCOMO3D code. The simulation results show that using these concretes in large reactor cavity would not provide sufficiently homogeneous cooling of the entire corium layer unless additional water distribution systems are installed.