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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May 2025
Nuclear Technology
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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. L. Pitner
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 77-85
Technical Paper | Material | doi.org/10.13182/NT76-A31626
Articles are hosted by Taylor and Francis Online.
Eighteen boron carbide specimens were irradiated for 355 effective full-power days in the Experimental Breeder Reactor II to maximum burnups of 82 x 1020 capture /cm3. Baseline specimens were patterned after Fast Flux Test Facility reference boron carbide, and material variables of 10B enrichment, pellet density, grain size, and stoichiometry were investigated in the test. Irradiation temperatures ranged from 1175 to 1570°F (635 to 855°C). Each specimen was individually instrumented to measure temperature and helium release continuously during irradiation.Postirradiation examination provided information on pellet integrity, swelling, tritium retention, and compatibility with stainless-steel containment components.