ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
DOE fast tracks test reactor projects: What to know
The Department of Energy today unveiled 10 companies racing to bring test reactors online by next year to meet Trump's deadline of next Independance Day, leveraging a new DOE pathway that allows reactor authorization outside national labs. As first outlined in one of the four executive orders on nuclear energy released by President Trump on May 23 and in the request for applications for the Reactor Pilot Program released June 18, the companies must use their own money and sites—and DOE authorization—to get reactors operating. What they won’t need is a Nuclear Regulatory Commission license.
J. A. Basmajian, A. L. Pitner, D. E. Mahagin, H. C. F. Ripfel, D. E. Baker
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 238-248
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31190
Articles are hosted by Taylor and Francis Online.
Fast neutron spectra irradiations of boron carbide are being performed. Hardened spectra irradiations in ETR, material irradiations in EBR-II, and EBR-II components yielded the data which are being used for design and analysis of FFTF control elements. Boron carbide was irradiated at temperatures from 800 to 1600°F at burnup values from 2 × 1020 to 20 × 1020 captures/cm3. A variety of material parameters such as pellet density and boron-to-carbon ratios were measured. Data on gas release, swelling, thermal conductivity, microscopy, and compatibility were found to differ substantially from data obtained in thermal reactors.