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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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
C. William Savery, Y. S. Huang, George M. Kowal
Nuclear Technology | Volume 27 | Number 3 | November 1975 | Pages 327-336
Technical Paper | Reactor | doi.org/10.13182/NT75-A24308
Articles are hosted by Taylor and Francis Online.
A computer code, MNODE, for predicting the state histories and inventories of an inert gas and water liquid and vapor flowing in a zoned containment has been developed. It employs a model that describes the unsteady flow and thermodynamics of two-phase two-component mixtures flowing among 12 connected control volumes. This calculational model can be applied to problems of hypothetical high-pressure primary coolant, feed water, or steam line ruptures in such structures as nuclear containments, tunnels, or auxiliary buildings. In comparison with previously reported zoned containment computation models, this model rigorously treats the thermodynamics of two-phase two-component mixtures of water and an inert gas, is provided with several flow model options including an inertia flow equation, and is demonstrated with substantial verification. Predictions are compared with the results of an analytical gas dynamic problem, semiscale blowdown experiments, and solutions to a subcompartment analysis standard problem by other computer codes in use within the nuclear industry.