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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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
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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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INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
Sung Sik Kang, In Sup Kim
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 336-343
Technical Paper | Material | doi.org/10.13182/NT92-A34641
Articles are hosted by Taylor and Francis Online.
The effect of dynamic strain aging (DSA) on fracture is investigated on the quenched and tempered specimens of American Society of Mechanical Engineers (ASME) standard SA508 class 3 nuclear pressure vessel steel. Serrated flow by DSA is observed between 180 and 340°C at a tensile strain rate of 2.08 × 10−4/s and 1.25 × 10−3/s. The DSA causes a sharp rise in the ultimate tensile strength and a marked decrease in ductility. The DSA range shifts to higher temperatures with increased strain rates. The temperature and strain rate dependence of the onset of serrations yields an activation energy of 16.2 kcal/mol, which suggests that the process is controlled by interstitial diffusion of carbon and nitrogen in ferrite. The Ji value obtained from the direct current potential drop (DCPD) method, for true crack initiation, is lowered by DSA. The drop in Ji at elevated temperatures may be because of the interaction of the interstitial impurities with dislocations at the crack front. Compared with JIC from American Society for Testing and Materials (ASTM) standard E813, the Ji by DCPD is a better parameter to use to detect the DSA effect on fracture toughness. Crack propagation is also affected in terms of the tearing modulus. The tearing modulus in dynamic strain aging is ∼30% smaller than that at room temperature.