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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.
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2024 ANS Annual Conference
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X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
J. V. Donnelly
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 180-184
Technical Note | doi.org/10.13182/NSE10-76
Articles are hosted by Taylor and Francis Online.
MCNP applies only nuclear data tabulated at specific temperatures and does not incorporate methods for general temperature interpolation of nuclear data. However, in models representing realistic power reactor cores, it is generally necessary to represent the distribution of fuel and coolant temperatures to reliably predict detailed power distributions and reactivity feedback effects. This paper describes methods that can be easily applied for the representation of cross-section data at general temperatures, based on interpolation through mixing of nuclide representations at multiple temperatures. The discrepancies due to the interpolations have been determined to be insignificant relative to the estimated uncertainties in typical calculated eigenvalues.