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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
Liqiang Hou, Dahuan Zhu, Qing Wu, Jian Deng, Xiao-li Wu (Nuclear Power Inst of China)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 578-583
The focusing effect of the metal molten pool plays an important role in elevating the validity of the In-Vessel Retention (IVR) during a severe accident while the melting of the shroud and basket can contribute to the formation of the metal molten pool. Therefore, the study on the melting behavior of the shroud and basket can offer technical support for the validity analysis of IVR. The method of computational fluid dynamics (CFD) has been used to establish a two-dimensional calculation model of the 1/8 core of ACP1000 to study the melting behavior of the shroud and basket during the severe accident of large LOCA. The core has been divided into ten nodes in the axial direction and the radiation model and the solidification and melting model have been considered during the calculation. The results show that the shroud at six out of ten nodes and the basket at five out of ten nodes have melted totally before the first significant migration of the core and that the basket always starts to melt after the shroud has melted totally at the same node.