ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Hu Mao, Bao-Wen Yang, Sipeng Wang
Nuclear Science and Engineering | Volume 193 | Number 1 | January-February 2019 | Pages 33-45
Critical Review – Selected papers from NURETH 2017 | doi.org/10.1080/00295639.2018.1525987
Articles are hosted by Taylor and Francis Online.
Subchannel analysis is widely used in nuclear reactor core thermal-hydraulic calculation and safety analysis. In subchannel analysis, the axial flow is usually treated as the dominant one-dimensional flow, and the lateral flow is simplified as the intersubchannel interactions and is modeled by introduction of semiempirical source terms or separate models. The accuracy of the subchannel analysis is strongly dependent on the modeling of intersubchannel interactions between adjacent subchannels. The intersubchannel interaction can be decomposed into three components: diversion cross flow that occurs due to imposed transverse pressure gradients, turbulent mixing that occurs due to stochastic pressure and flow fluctuations, and void drift that results from lateral migration of the gaseous phase (void) due to a strong tendency of the two-phase system approaching the equilibrium state of phase distribution. This critical review focuses on void drift research. Both experimental observation of the void drift phenomenon and the proposed void drift models are reviewed. The improvements and corresponding assessments of the void drift models are summarized. Following that, further improvements on the void drift model are proposed.