ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
Filippo D’Annucci, Elma Beth S. Pardue, Wilfried Rommelaere, Günter Bäro
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 9-13
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A33048
Articles are hosted by Taylor and Francis Online.
To investigate the tritium content in the various components and to determine the 10B burnup, a postirradiation examination was carried out on three burnable poison rods that had been irradiated in the first cycle of the Oconee 2 Reactor. The results of the analysis reveal that the Al2O3-B4C pellets retain the major portion 099%) of all the tritium generated; only a very small quantity (<0.5%) of the tritium produced is absorbed by the cladding and no tritium was detected in the plenum gas. Comparison of the average postirradiation 10B content with the preirradiation content indicates that almost all of the 10B has been consumed. The experimental results are in good agreement with the calculated tritium content of an irradiated poison rod.