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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Latest News
Blades-in turbine inspections at Quad Cities set new benchmark for Constellation
When Constellation decided to install replacement Alstom low-pressure turbines at three of its boiling water reactor plants more than 15 years ago, one benefit was knowing the new turbines should operate reliably—and without major inspections—for several years.
Vineet Kumar, Zhiee Jhia Ooi, Caleb S. Brooks (Univ of Illinois)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 68-76
A new database of steam water flow in a vertical annulus is under development in the Multiphase Thermofluid Dynamics Laboratory (MTDL) at the University of Illinois at Urbana-Champaign. The focus of the dataset is on the two-phase phenomena of condensing, flashing, and saturated flow in a vertical channel. The 2.03 m annular channel with inner and outer diameter of 19.1 mm and 38.1 mm respectively is located downstream of an internally heated annular section. Five measurement ports in this unheated section provide measurement of pressure and local measurements of void fraction, interfacial area concentration, gas velocity, Sauter mean diameter, and liquid temperature. The dataset was designed for validation of onedimensional system codes and multi-dimensional computational fluid dynamics codes. The focus of the adiabatic steam-water flow fills an important gap in validation data between the simplified hydro-dynamic data of air-water flow and the complex thermo-fluid dynamic data of boiling flows.