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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
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.