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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
DOE awards $134M for fusion research and development
The Department of Energy announced on Wednesday that it has awarded $134 million in funding for two programs designed to secure U.S. leadership in emerging fusion technologies and innovation. The funding was awarded through the DOE’s Fusion Energy Sciences (FES) program in the Office of Science and will support the next round of Fusion Innovation Research Engine (FIRE) collaboratives and the Innovation Network for Fusion Energy (INFUSE) awards.
Takuya Nagasaka, Haiying Fu, Nobuyuki Kometani, Takeshi Miyazawa, Takeo Muroga, Hideo Watanabe, Masanori Yamazaki, Takeshi Toyama
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 645-651
Technical Paper | doi.org/10.1080/15361055.2017.1352428
Articles are hosted by Taylor and Francis Online.
In order to investigate the effect of post-weld heat treatment (PWHT) and post-irradiation annealing (PIA), electron-beam-weld specimens of the reference low activation vanadium alloy, NIFS-HEAT-2, were neutron-irradiated to a fluence of 7.62 × 1023 neutron m−2 (E > 1 MeV) at 563 K in Belgian Reactor-2. In the present experiments, unexpected oxidation of the surface of the samples occurred during the neutron irradiation, and significantly degraded impact properties of the weld metal, while the degradation was not significant for the base metal. The removal of the oxidized layer by electro-polishing improved the impact properties of the weld metal. Although complete removal of the oxidized layer could not be confirmed, it is revealed that impact absorbed energy of the weld metal with post-weld heat treatment at 1073 K was comparable to that of the base metal after the post-irradiation polishing. In other words, irradiation embrittlement of the weld metal was successfully suppressed by the PWHT. PIA at 773 K and above was effective to recover the irradiation hardening and irradiation embrittlement. Mechanisms of the irradiation hardening, irradiation embrittlement and its recovery were discussed.
