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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
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.
