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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.
Yoshiro Asahi, Keisuke Okumura, Yasuo Ose
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 78-95
Technical Paper | doi.org/10.13182/NSE01-A2223
Articles are hosted by Taylor and Francis Online.
The rate equation for neutronic population is derived from the transient neutron diffusion equation. Neutronic imbalance is defined as the difference between the solution of the rate equation and the neutronic population obtained by spatial kinetics. If the transient neutron diffusion equation in the fully implicit formulation is discretized in such a manner as to satisfy the Gauss theorem and to retain a conservation form, neutronic imbalance decreases as the convergence criteria become strict. The iterative implicit method for neutronics and thermal hydraulics requires continuity of all the variables involved, which, in turn, facilitates the automatic time-step width control. From the viewpoints not only of well-posedness of a transient problem but also of code verification, a transient code should be capable of a null transient analysis for stable systems. Sample calculations are performed for a pressurized water reactor main-steam-line-break accident. An overall thermal-hydraulic trend model is conjectured to help compare and explain the calculated results. Spatial kinetics is found to clearly influence even the temporal behaviors of the secondary system.