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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
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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
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.