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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.
V. J. Tennery, J. L. Botts
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 264-272
Technical Paper | Fuel | doi.org/10.13182/NT72-A31081
Articles are hosted by Taylor and Francis Online.
Chemical analysis techniques were demonstrated for three uranium nitride specimens. Sintered uranium mononitride (UN), unsintered UN powder, and UN1.572 powder were analyzed for the major constituents, and a mass balance of 100.00 ± 0.03% was realized in every case. The gravimetric determination of uranium in these materials by an oxidation-reduction-oxidation method gave good precision and accuracy. Results from the direct oxidation method were strongly dependent on the oxygen content of the gas used to oxidize the sample. The controlled-potential cou-lometric method was used to confirm the gravimetric uranium results. The Dumas method for nitrogen determinations was shown to be superior to the Kjeldahl for both UN and UN1.572. Inert gas fusion is suitable for the determination of oxygen and a conventional combustion method is suitable for carbon determinations. Sintered UN provided a mass balance of 99.989% with a mole ratio N+O + C/U = 0.997 and a crystal lattice parameter a = 4.8896 ± 0.0001 Å. The micro structure of this sample consisted of single phase mononitride.