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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
J. C. Carter, R. T. Purviance, J. F. Boland, C. E. Dickerman, J. E. Hanson
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 133-145
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31128
Articles are hosted by Taylor and Francis Online.
The Argonne Mark-II loop in the core of the TREAT reactor is used to investigate the thermodynamics of a sodium-cooled fast reactor fuel pin. This experiment on the top 30.44 cm of an unirradiated fast test reactor (FTR) fuel pin was the first in a series to be conducted in support of the liquid metal fast breeder reactor (LMFBR) program and as such constituted an exploration into the ability of the loop and reactor facility to produce simulations of a wide range of flow conditions in assemblies of sodium-cooled fast reactor fuel pins. The objective of this first experiment (L1) was to approach but not cross over the threshold of the structural integrity of the cladding by reducing the sodium velocity while the pin was continuing to generate heat at the full power +20% rate of an FTR pin. This objective was achieved despite perturbations in sodium velocity and temperature of greater amplitude and frequency than anticipated and with some irreversible structural changes in the pin.