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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
A. Calza-Bini, G. Cosoli, G. Filacchioni, M. Lanchi, A. Nobili, E. Pesce, U. Rocca, P. L. Rotoloni
Nuclear Technology | Volume 25 | Number 1 | January 1975 | Pages 103-112
Technical Paper | Fuel | doi.org/10.13182/NT75-A24353
Articles are hosted by Taylor and Francis Online.
The heat transfer coefficient between fuel and cladding has been measured in-pile for different types of Zircaloy-2 sheathed fuels: UO2 and UO2-PuO2 pellets, UO2 Vipac, and UO2-PuO2 Sphere-Pac sol-gel. The samples were tested in (a) instrumented rigs, in which fuel and cladding temperatures and nuclear and gamma-ray generated power were directly and continuously measured up to a heat rating of 500 W/cm, and in (b) a hydraulic rabbit at very high rating (over 1000 W/cm). Semiempirical correlations starting from known models of fuel/clad heat transfer, based on strong or weak fuel/clad interaction, fuel cracking, and decrease in gap conductance due to oxide micro layer formation on the cladding internal surface, have been set up to fit the experimental data.
