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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Transport by Barge and Road: Shipping Crystal River’s Segmented RPV to Disposal
The Optimized Segmentation process patented by Orano Decommissioning Services was successfully implemented for the first time at the Crystal River Unit 3 (CR-3) decommissioning project in Florida [1]. Using this approach, Orano was able to avoid the time- and resource-intensive process of packaging components into numerous standardized waste containers and significantly reduced the required segmentation activities.
Mohan S. Yadav, Seungjin Kim
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 94-105
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics | doi.org/10.13182/NT13-A15759
Articles are hosted by Taylor and Francis Online.
The present study focuses on developing a database to investigate the effects of 90-deg vertical elbows on the transport and distribution of local two-phase flow parameters in air-water bubbly flows. The experimental facility consists of both vertical and horizontal sections made out of 50.8-mm inner diameter pipes and interconnected via 90-deg glass elbows. Six different flow conditions within or near the bubbly flow regime at the inlet are investigated in the current study. A multisensor conductivity probe is employed to measure detailed local two-phase flow parameters at ten axial locations along the test section, within which 90-deg elbows are installed at L/D = 63 and 244.7 from the inlet. The data show that the elbow makes a significant impact on the two-phase pressure drop, bubble distribution, and bubble velocity. The bubbles moving across the vertical-upward elbow are entrained along the secondary flow streamlines leading to a bimodal distribution. For the test conditions investigated in the present study, this bimodal distribution is independent of the bubble distribution upstream of the vertical-upward elbow. In the case of the vertical-downward elbow, on the other hand, the large inertia of the axial liquid flow results in the bubbles migrating toward the inside of the elbow curvature.