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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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 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.
Yi Xu, Hong Li, Feng Xie, Jianzhu Cao, Jiejuan Tong
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 671-678
Technical Note | doi.org/10.1080/15361055.2017.1290949
Articles are hosted by Taylor and Francis Online.
The Very High Temperature Reactor (VHTR) is one of the six proposed Generation IV reactor concepts. The HTR-10, a 10 MW high temperature gas-cooled reactor was a helium cooled, graphite-moderated, and thermal neutron spectrum reactor. Since tritium (H-3) has an effect on the environment and public radiation dose, it has received more and more attention in the environmental impact assessment of nuclear facilities. Recently, several experiments on source terms in HTR-10 have been run, of which preliminary measurements indicated H-3 was an important nuclide in the primary loop of HTR-10. The production mechanism, distribution characteristic, reduction route, and release type of total H-3 in HTR-10 were analyzed and discussed in this technical note. A theoretical model was established to calculate the total activity of H-3 in the reactor core and activity concentration of H-3 in the primary loop of HTR-10. This model indicated that the majority of total H-3 was produced by ternary fission reactions and H-3 in the primary helium was mainly generated from activation reactions of impurities in the reactor core. The research results can provide useful information for the experimental measurement of H-3 in HTR-10, and promote the study of H-3 in high temperature gas-cooled reactors (HTGRs).