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Two steps forward for U.K. advanced nuclear
This week, two significant announcements have emerged from the United Kingdom’s advanced reactor sector.
On June 14, Rolls-Royce, the United Kingdom National Nuclear Laboratory, and the Japan Atomic Energy Agency announced that they had signed two trilateral memorandums of cooperation to collaborate on “advanced modular reactor (AMR) technology, specifically high-temperature gas-cooled reactors (HTGR), and the coated particle fuel these reactors will use.”
Separately, on June 16, Bellevue, Wash.–based TerraPower announced that its Natrium reactor design has been formally submitted for U.K. regulatory review. The company also announced the formation of a new subsidiary, TerraPower UK Ltd.
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.