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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
March 2026
Fusion Science and Technology
Latest News
Chernobyl at 40 years: Looking back at Nuclear News
Sunday, April 26, at 1:23 a.m. local time will mark 40 years since the most severe nuclear accident in history: the meltdown of Unit 4 at the Chernobyl nuclear power plant in Ukraine, then part of the Soviet Union.
In the ensuing four decades, countless books, documentaries, articles, and conference sessions have examined Chernobyl’s history and impact from various angles. There is a similar abundance of outlooks in the archives of Nuclear News, where hundreds of scientists, advocates, critics, and politicians have shared their thoughts on Chernobyl over the years. Today, we will take a look at some highlights from the pages of NN to see how the story of Chernobyl evolved over the decades.
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.