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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
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.
Emilio Baglietto, Hisashi Ninokata
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 237-248
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3839
Articles are hosted by Taylor and Francis Online.
An improved quadratic nonlinear eddy viscosity model (NLEVM) is introduced that respects the constraints of realizability for calculation of detailed coolant velocity and temperature distributions inside tight lattice fuel bundles. The model adopts an optimized low-Reynolds formulation based on direct numerical simulation data, combined with an enhanced nonlinear stress-strain relationship to correctly capture the anisotropy of the flow up to the solid wall. The capabilities of the model are first assessed on the prediction of fully developed flow inside triangular lattice bundles; it is shown how the ability to correctly reproduce the turbulent-driven secondary flow enables the model to accurately reproduce wall shear stress and velocity distributions inside the bundle. The model is applied to the evaluation of the thermal-hydraulic performances of novel fuel designs, discussing potential advantages and limitations of the newly proposed solutions.