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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee, I. A. Mudawwar
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 213-226
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34242
Articles are hosted by Taylor and Francis Online.
A theoretical critical heat flux (CHF) model based on microlayer dryout and Helmholtz instability for subcooled tube flow under pressurized water reactor operation conditions is first extended to the conditions of saturated low-quality flow. Then the applicability of this extended theoretical CHF model to rod bundles is evaluated. The effects of grid spacers, cold wall, and axial heat flux nonuniformity on bundle CHFs are investigated. The extended CHF model is very accurate when compared with three other well-known CHF correlations on a data base of round tube CHF. In the simple case with uniform axial heat flux distribution, simple grid spacers, and no guide tubes in bundles, the theoretical CHF model gives good results. In other more complex cases, the cold-wall effects due to the existence of guide tubes, the effects of mixing vane grids, and the effects of nonuniform axial heat flux distributions on CHF are significant. The present model generally gives satisfactory results when compared with ∼1400 bundle CHF experimental data points although corrections for grid spacers, cold wall, and axial heat flux have not yet been considered.