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
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
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
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!
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Nuclear Science and Engineering
November 2021
Nuclear Technology
Fusion Science and Technology
August 2021
Latest News
Hanford completes wastewater basin work to support tank waste treatment
Record-breaking heat and the vast size of the job did not stop the Department of Energy’s Office of River Protection and its tank operations contractor, Washington River Protection Solutions (WRPS), from completing a construction project critical to the Hanford Site’s Direct-Feed Low-Activity Waste program for treating radioactive tank waste.
S. Nogami, K. Yamamoto, M. Fukuda, A. Hasegawa
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 601-606
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST14-927
Articles are hosted by Taylor and Francis Online.
To improve the fatigue life assessment of the relatively thin wall structure of the fusion reactor blanket, the fatigue micro-crack initiation behavior of the F82H steel at room temperature was investigated. The micro-crack initiation life was approximately 20–30 % of the fatigue life. The crack initiation was observed at the prior austenitic grain boundary, the packet boundary, the block boundary, and the inside of the block structure. The majority was the transgranular crack initiation, which exceeded 90 % of the all. The effect of the irradiation damage (irradiation hardening) was only a shortening of the micro-crack initiation life. No change of the micro-crack initiation sites and their ratio were observed.
