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
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jul 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
August 2026
Fusion Science and Technology
Latest News
GAO report describes cleanup progress at Moab Mill Site
A new report released by the U.S. Government Accountability Office states that the Department of Energy’s Office of Environmental Management (EM) has disposed of more than 16 million tons of radioactive and hazardous waste from the Moab Mill Site. While cleanup continues at the Cold War–era uranium ore processing site in southeastern Utah, a plan for the next phase of groundwater remediation is still needed, according to the GAO.
J. Bentley, F. W. Wiffen
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 376-384
Technical Paper | Uranium Resource / Material | doi.org/10.13182/NT76-A31651
Articles are hosted by Taylor and Francis Online.
Vanadium-base alloys, V—10% Cr, V—20% Ti, and VANSTAR-7, alloys with potential for fusion reactor application, have been irradiated in the Experimental Breeder Reactor II in the temperature range of 400 to 800°C, mainly to a fluence of 1.5 × 1022 n/cm2 (>0.1 MeV). Swelling determined both from immersion density measurements and void distribution data obtained by transmission electron microscopy showed that the V—20% Ti was completely resistant to void formation for these irradiation temperatures and for the highest fluence achieved, 6 × 1022 n/cm2. Voids formed in both the V—10% Cr and VANSTAR-7 alloys, but only the V—10% Cr, irradiated at 690 and 805° C, showed technologically significant swelling, near 1%. Swelling in this alloy at lower temperatures and in VANSTAR-7 at all temperatures was below 0.1%. Dislocation structures were complex in all three alloys. In the V—20% Ti, the scale of the dislocation network coarsened with increasing irradiation temperature. In the other two alloys, the scale of the damage, both dislocation and void components, was similar for irradiation at 496 and 580°C, but coarsened considerably to produce similar structures for irradiations at 690 and 805°C. In many cases, detail of the microstructure was obscured by strongly diffracting zones that are believed to be impurity related. Of the three alloys examined, V—20% Ti possesses the greatest swelling resistance for the irradiation temperatures and fluences achieved and thus is judged to have the greatest potential for use in fusion reactors.