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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
W. Yao, D. Bestion, P. Coste, M. Boucker
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 129-142
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3665
Articles are hosted by Taylor and Francis Online.
A three-dimensional (3-D) two-fluid model for a turbulent stratified flow with and without condensation is presented, in view of investigating pressurized thermal shock (PTS) scenarios when a stratified two-phase flow takes place in the cold legs of a pressurized water reactor. A modified turbulent K-[curly epsilon] model is proposed with turbulence production induced by interfacial friction. A model of interfacial friction based on an interfacial sublayer concept and three interfacial heat transfer models - namely, a model based on the small eddies-controlled surface renewal concept, a model based on the asymptotic behavior of the eddy viscosity, and a model based on the interfacial sublayer concept - are implemented into a preliminary version of the NEPTUNE code based on the 3-D module of the CATHARE code. As a first step, the models are evaluated by comparison of calculated profiles of velocity, turbulent kinetic energy, and turbulent shear stress with data in a turbulent air-water stratified flow in a rectangular channel and with data for a water jet impacting the free surface of a water pool. Then, a turbulent steam-water stratified flow with condensation is calculated, and some first conclusions are drawn on the interfacial heat transfer modeling and on the applicability of the model to PTS investigations.