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
Work advances on X-energy’s TRISO fuel fabrication facility
Small modular reactor developer X-energy, together with its fuel-developing subsidiary TRISO-X, has selected Clark Construction Group to finish the building construction phase of its advanced nuclear fuel fabrication facility, known as TX-1, in Oak Ridge, Tenn. It will be the first of two Oak Ridge facilities built to manufacture the company’s TRISO fuel for use in its Xe-100 SMR. The initial deployment of the Xe-100 will be at Dow Chemical Company’s UCC Seadrift Operations manufacturing site on Texas’s Gulf Coast.
H. E. McCoy, Jr., J. R. Weir, Jr.
Nuclear Science and Engineering | Volume 25 | Number 4 | August 1966 | Pages 319-327
Technical Paper | doi.org/10.13182/NSE66-A18551
Articles are hosted by Taylor and Francis Online.
It has been shown that the aluminum alloy 6061 in the fully annealed, cold-worked, and age-hardened conditions undergoes very small changes in the tensile properties as a result of neutron irradiation to doses on the order of 1019 fast n/cm2( > 2.9 MeV) and 1020 thermal n/cm2. At irradiation temperatures above 115°C, no changes in properties are observed. The small property changes observed when the material is irradiated at 43°C are mostly annealed out after ½ at 200°C. These changes are rationalized in terms of the precipitate particles present in the alloy and the mobility of the irradiation-induced defects.
