ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Michael P. Manahan
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 295-315
Technical Paper | Material | doi.org/10.13182/NT83-A33289
Articles are hosted by Taylor and Francis Online.
A Miniaturized Disk Bend Test (MDBT) capable of extracting postirradiation mechanical behavior information from disk-shaped specimens no larger than those used for transmission electron microscopy has been successfully developed. Finite element analysis is performed to convert the experimentally measured data into useful engineering information. A new finite element frictional contact boundary condition model has been developed that is essential in modeling the non-uniform strain fields present in the MDBT specimen. The MDBT methodology has been shown to be capable of delivering uniaxial stress/strain information with approximately the same level of accuracy as that present in the more conventional uniaxial tensile testing approach. A data inversion strategy has been developed and applied to irradiated materials to determine uniaxial tensile behavior. Since neutron irradiation costs scale with specimen volume, this miniaturized mechanical behavior test can now provide significant savings in irradiation testing costs for nuclear materials used in fusion and other nuclear technologies. In addition, it is now possible to provide mechanical behavior information not ordinarily obtainable due to space limitations in irradiation experiments, and thus expedite alloy development investigations.