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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Nicholas Tsoulfanidis—ANS member since 1969
We welcome ANS members who have careered in the community to submit their own Nuclear Legacy stories, so that the personal history of nuclear power can be captured. For information on submitting your stories, contact nucnews@ans.org.
As an undergraduate I studied physics at the University of Athens. I entered the university in 1955 after successfully passing a national exam (came up fourth in a field of about 700 candidates). Upon graduation and finishing my mandatory two-year military service, the plan was to teach physics either in a public high school or as a tutor for a private for-profit institution, preparing high school students for the national exam.
Chaoliang Xu, Xiangbing Liu, Yuanfei Li, Wangjie Qian, Wenqing Jia, Qiwei Quan, Jian Yin
Nuclear Technology | Volume 208 | Number 6 | June 2022 | Pages 1083-1088
Technical Note | doi.org/10.1080/00295450.2021.1997058
Articles are hosted by Taylor and Francis Online.
Nitrogen ion implantation can be used to improve the surface mechanical properties of austenitic stainless steel. In this study, austenitic stainless steel was irradiated with 1.1 MeV N ions at room temperature up to 15 displacements per atom. Then the microstructural and mechanical properties were studied by grazing incidence X-ray diffraction and nano-indenter. A finer synchrotron radiation diffraction pattern is obtained compared with traditional X-ray diffraction, indicating an expanded austenite phase γN and CrN phase after being irradiated to several damage levels. An irradiation-induced martensite phase appears first and then disappears with increased damage. The enrichment of the nitrogen supply in austenitic stainless steel can explain this phenomenon. The hardness data show an irradiation hardening phenomenon. Two different inflexion points hc1 and hc2 in H2 versus 1/h curves are observed, and the real hardness of the irradiation damaged layer can be obtained from the H2 versus 1/h curve between hc1 and hc2.