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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Hiroshi Kawamura
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 246-255
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31642
Articles are hosted by Taylor and Francis Online.
In a reactor transient analysis, the friction factor and the heat transfer coefficient are assumed equal to the steady-state values, even in a transient state. The transient turbulent flow in a circular tube subjected to a step change of pressure gradient is calculated numerically. Transient variations of the friction factor and the heat transfer coefficient are obtained. Effects of the Reynolds number and a wall heat capacity are also examined. The quasi-static momentum equation is found to be approximately valid for both accelerated and decelerated turbulent flows. The quasi-static energy equation is valid for flow transients of gas-cooled reactors.