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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.
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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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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.
A. R. Raffray, F. Escourbiac, F. J. Fuentes, L. Giancarli, B. Macklin, A. Martin, M. Merola, R. Mitteau, J. Palmer
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 465-476
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-945
Articles are hosted by Taylor and Francis Online.
The overall programmatic objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The physics part of this objective (including burning plasma, Q of at least 10 and stationary conditions) seems to be well appreciated by the scientific community internationally. However, there seems to be less of an emphasis on the fusion technology part of the objective, which includes demonstrating the availability and integration of technologies essential for a fusion reactor and testing components including tritium breeding blanket modules for a future reactor. In fact important technology information will be obtained from the design, fabrication and operation of the vacuum vessel and out-of-vessel systems such as magnets, tritium system, cryogenic systems, cooling water systems, and associated safety aspects. In addition, DEMO-relevant information will be obtained from the operation of breeding blanket test modules in ITER. Moreover valuable information applicable to DEMO and beyond will also be obtained in a number of areas linked to in-vessel components. This paper summarizes the DEMO-relevant fusion technology information that will be obtained from ITER with a major focus on the areas linked to in-vessel components.