ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
J. A. Mowrey, P. R. Boylan, S. I. Abdel-Khalik
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 223-242
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2922
Articles are hosted by Taylor and Francis Online.
A RELAP5/MOD3.1 model of a boiling water reactor and an interface originally developed as a real-time test platform for the Browns Ferry Unit 2 feedwater control system and turbine governors have been expanded to include feedwater heater systems and controls and to change the reactor recirculation pump controls from the current fluid-coupled drive to a future variable speed drive. The expanded model includes feedwater heater shell-side components, associated piping, steam supplies, and condensers, and allows simulation of the Foxboro digital feedwater heater level control system. The model was updated to RELAP5/MOD3.1.1, while the interface was expanded to handle additional communications and operator actions. The simulated feedwater heater level controls were tuned and benchmarked; benchmarking was performed against steady-state data at various power levels from plant heat balance data. After the model was benchmarked, various transients were simulated to identify potential flaws in the feedwater heater level control system.