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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
Haidong Liu, Deqi Chen (Chongqing Univ), Xiang Zhang (State Nuclear Power Technology Research & Development Center)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 460-473
Computational fluid dynamics (CFD) research of flow boiling and heat transfer in single rod channel is carried out based on RPI wall boiling model by CFD code Fluent. The numerical model is validated with published experimental date. According to numerical results, it can be seen that the numerical model is able to calculate the cross sectional averaged void fraction in a vertical tube. The visualization experiments of flow boiling will be performed in the near future to investigate the boiling characteristics of a vertical square channel with one heating rod. However, due to the limitations of measuring methods, visualization experiments can only be performed to obtain local visualization data, but local flow field characteristic parameters are difficult to obtain. Therefore, in order to deeply understand the boiling mechanism, the local flow characteristics including the distribution of void fraction, liquid temperature as well as velocities, a numerical study are performed to investigate the characteristics mentioned above, and detailed analysis are presented in this paper. In this study, the heat flux is the possible critical heat flux under corresponding working condition based on Bowring correlation; and the purpose of this work is focusing on the flow boiling and heat transfer when the heat flux is approaching critical heat flux. This work is meaningful for the subsequent integration on the mechanism of boiling two-phase flow.