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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
H. Ueda et al.
Fusion Science and Technology | Volume 63 | Number 1 | May 2013 | Pages 316-318
doi.org/10.13182/FST13-A16940
Articles are hosted by Taylor and Francis Online.
This paper describes the initial result of simulation study of neutron production by NBI heating in the GAMMA 10 tandem mirror by using a buildup numerical simulation code. In the GAMMA 10 central-cell, high energy ions have localized in the neutral beam injection port and the other bounce point due to the perpendicular injection. By considering this mechanism, the position of the test zone for neutron irradiation is assumed and the amount of the neutron flux is evaluated. The neutron flux is about 1.3 kW/m2, for high-density mode and about 1.2 kW/m2, for hot-ion mode.