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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
NRC nominee Nieh commits to independent safety mission
During a Senate Environment and Public Works Committee hearing today, Ho Nieh, President Donald Trump’s nominee to serve as a commissioner at the Nuclear Regulatory Commission, was urged to maintain the agency’s independence regardless of political pressure from the Trump administration.
X. N. Hao, J. J. Sha, J. X. Dai, J. Li, J. Lv, X. L. Yang, H. K. Yoon
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 163-170
Technical Paper | doi.org/10.13182/FST13-761
Articles are hosted by Taylor and Francis Online.
Tungsten and CuCrZr alloy have been considered as the potential candidates for armor and heat sinking materials of plasma-facing components (PFCs) because of their attractive mechanical, nuclear and physical properties. However, due to the incompatibility of the coefficient of thermal expansion and the elastic properties between the W and the Cu alloy as well as the nonhomogeneous temperature distribution in PFCs, one of the crucial issues is the generation of thermal stresses in W/CuCrZr PFCs on cooling either during fabrication or during operation of a fusion reactor. In the current work, the thermo-mechanical analysis of W/Cu-alloy joints, where a compliant OFHC-Cu with different thickness was used as an interlayer, was carried out by using finite element method (FEM) under various conditions including the fabrication process and steady and transient operation.