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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
A. Calza-Bini, G. Cosoli, G. Filacchioni, M. Lanchi, A. Nobili, U. Rocca, P. L. Rotoloni
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 208-216
Technical Paper | Material | doi.org/10.13182/NT74-A31391
Articles are hosted by Taylor and Francis Online.
Irradiation experiments carried out by the Comitato Nazionale Energia Nucleare to evaluate the thermal behavior of different types of fuel are described. The integral thermal conductivity has been measured continuously during the irradiation. The fuel temperatures have been detected by thermocouples, and total power has been measured by a colorimetric system able to detect separately the nuclear and gamma-ray power. The integral thermal conductivity curve versus temperature has been found for the UO2 pelletized and vibrocompacted (Vipac) powder and for the UO2-PuO2 pelletized and Sphere Pac sol-gel; the accuracy is between 10 and 12%. Differences have been found, for all materials tested, between the data at the first startup and the data measured during the following life; the differences between Vipac and pelletized samples decrease after the first startup because of the restructuring of the material.