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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Shuai Wang, He Xue, Guiyi Wu, Zheng Wang, Kuan Zhao, Chenqiang Ni
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 623-632
Technical Paper | doi.org/10.1080/00295639.2022.2123210
Articles are hosted by Taylor and Francis Online.
Low alloy steel SA508 autogenously welded with Type 309L/308L austenitic stainless steel cladding is one of the common forms of the dissimilar metal weld joint (DMWJ) in the primary water of a pressurized water reactor (PWR). Accurate evaluation of the inhomogeneous mechanical propriety and crack growth driving force at the corresponding place on the DMWJ is important for integrity analyses of a PWR. In this study, the mechanical propriety of the DMWJ was obtained using a combined Vickers hardness test and the stress-hardness relationship. And, a finite element (FE) model for the DMWJ in a PWR with continuous transition mechanical propriety was built using a predefined temperature field method. Based on consideration of the heterogeneity mechanical properties on the DMWJ with the continuous transition mechanical propriety, the Mises stress distribution and J integral on the crack tip with different crack lengths was analyzed using elastoplastic FE analysis. As shown by the distribution profile of the Mises stress distribution and J integral on the crack tip, the inhomogeneous mechanical propriety distribution is found to significantly affect the crack driving force when the crack tip is close to the fusion boundary.