ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Renan Cunha, Claubia Pereira, Daniel Campolina, Maria Auxiliadora Fortini Veloso
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 361-366
Modeling and Simulations | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13446
Articles are hosted by Taylor and Francis Online.
GB is a linking code developed at the Departamento de Engenharia Nuclear/UFMG to couple MCNP with the depletion and burnup capability of ORIGEN2.1. In the first version of GB, code described the behavior during the burn up of only 25 isotopes. The amount of isotopes to be considered in the simulation was increased in the GB version used in this paper (named GB5). It was simulated 75 time steps at 800kw of a Heat Pipe Power System model. Results showed that GB5 is able to generate very similar results compared to MCNPX2.6.0. The small difference encountered with the neutron flux parameter between GB5 and MCNPX2.6.0 is explained by the form that recoverable energy per fission is calculated in GB5. Radiotoxicity and radioactivity results are also presented.