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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.