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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.
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Orlando, FL|Renaissance Orlando at SeaWorld
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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
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
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.