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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Disa seeks NRC license for its uranium mine waste remediation tech
The Nuclear Regulatory Commission has received a license application from Disa Technologies to use high-pressure slurry ablation (HPSA) technology for remediating abandoned uranium mine waste at inactive mining sites. Disa’s headquartersin are Casper, Wyo.
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 | 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.