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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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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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Latest News
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.
Mohamed S. El-Genk, Richard L. Moore
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 354-373
Technical Paper | Nuclear Fuel Cycle Education Module / Nuclear Safety | doi.org/10.13182/NT81-A32644
Articles are hosted by Taylor and Francis Online.
The safe containment of molten core debris following a hypothetical meltdown accident in a light water reactor depends on the post-accident distribution and freezing of the debris on cold core structures. A one-dimensional physical model was developed to study the transient freezing of the molten debris on the inner surface of the test shroud wall in a severe, reactivity initiated accident in-pile experiment, and to assess the potential for wall melting upon being contacted by the molten debris. The conditions of finite wall thickness, convective cooling at the wall outer surface, radiative cooling of the debris, temperature-dependent thermophysical properties, and internal heat generation in the debris were considered. It is concluded that the shroud wall should not melt upon contact by the molten debris, which agreed with the experimental observations, because of the initial low temperature of the wall (538 K) and of the molten debris (∼3500 K) at the time of contact. Should wall melting occur, however, the wall molten layer would be unstable because of the small thickness of the wall and the continuous cooling at the wall outer surface by coolant bypass flow. The agreement between the calculations and experimental results indicated that considering the molten debris during the freezing process as a homogeneous mixture of the constituents (UO2 and Zircaloy) was a reasonable assumption.