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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Kathryn Huff stepping down from DOE Nuclear Energy post
Huff
After serving two years as the Department of Energy’s assistant secretary for Nuclear Energy, Kathryn Huff will vacate that position on May 3 and return to teaching. Huff had started at the DOE in May 2021, serving for one year as the principal deputy assistant secretary for Nuclear Energy
“Serving in this capacity has been an unparalleled privilege, and I’m immensely grateful for the opportunity to have worked alongside you--the dedicated and talented public servants in Nuclear Energy, in DOE, and across the Biden-Harris Administration,” Huff wrote in an email announcement to colleagues last week. “I chose this timing to enable the smoothest transition back to my professorship at the University of Illinois at Urbana-Champaign where my beloved research, students, husband, and dog await.”
Sunil Kumar Jatav, Vijay Kumar Pandey, Parimal P. Kulkarni, Arun K. Nayak, Upender Pandel, Rajendra K. Duchaniya
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1756-1768
Technical Paper | doi.org/10.1080/00295450.2022.2061291
Articles are hosted by Taylor and Francis Online.
To mitigate severe accidents in nuclear reactors, the present research sheds light on the melt-coolability behavior of corium with hypothetical experiments that have been performed at two different nozzle diameters under bottom flooding conditions. In this research, a simulant material CaO-Fe2O3 powder mixture was melted and poured into the test section that was embedded in the test facility (using a bottom pouring furnace instead of a tiltable furnace). Then, from the bottom of the melt pool, water was flooded through a nozzle at a pressure of 0.70 bar and a water flow rate of 12 liters per minute. Because of the interaction between the water and melt, the melt quenched and converted into fine porous debris, and the temperature history was recorded using 12 K-type thermocouples connected to a data acquisition system. The average quenching time and porosity of the debris were affected by variations in the nozzle diameter. This research will help in understanding real core-melt accidents that generally occur in nuclear power plants.
