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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Niranjan Gudibande, Kannan Iyer
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 674-683
Technical Paper | doi.org/10.13182/NT16-40
Articles are hosted by Taylor and Francis Online.
Radioactive materials are transported in hollow steel casks filled with lead. The lead in these casks can melt in an accidental fire during transportation leading to an increase in its volume. This plastically deforms the steel shell housing the lead. When the cask subsequently cools after the fire is extinguished, voids will form in the solidified lead. This work deals with the simulation of solidification with void formation in these transportation casks. In these simulations, one has to deal with solid-liquid and void-material interfaces. Solid-liquid movement during solidification is treated using a modified enthalpy method. The void that is formed in the solidified lead is assumed to be a vacuum. Consistent with this assumption, the boundary conditions of zero pressure and zero stress are imposed on the interface. The growth of the void is handled using the volume of fluid method. The methodology is first benchmarked by comparing the simulations with some experimental results available in the literature. Simulations are then performed for solidification in the transportation cask to study the effect of orientation on the void formation. A methodology is then developed to quantify the overall shielding effectiveness of the cask in terms of the total amount of radiation leaked.