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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
V. O’Donnell, T. Keya, A. Romans, G. Harvill, M. Andurkar, B. C. Prorok, S. M. Thompson, J. Gahl
Nuclear Technology | Volume 209 | Number 2 | February 2023 | Pages 254-260
Technical Note | doi.org/10.1080/00295450.2022.2120321
Articles are hosted by Taylor and Francis Online.
Experimentally characterizing radioactive materials can be time consuming and expensive. This is mainly due to the size requirements of inspected specimens. Due to the growing interest in using additively manufactured components in next-generation reactors, there is an urgent need to develop new accelerated testing techniques with regard to characterizing radiation damage. This will ensure a more timely certification of the unique material structures inherent to additively manufactured parts. In this study, we investigate a means to reduce the time investment, and thus the human exposure to radioactive specimens in need of experimental characterization. We determine the feasibility of using ultra-small specimens in lieu of much larger specimens to characterize bulk material properties before and after irradiation. Experiments were conducted to investigate this technique and compare it to conventional bulk irradiations and characterization activities. It was found that discernable radiation damage existed in the ultra-small specimens even after relatively short neutron irradiation times. The results also demonstrate decreased radiation hardening in additive manufactured Inconel 625 material relative to its wrought forms.