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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
Standards Program
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.
G. S. Brunson, R. M. Fryer, R. V. Strain
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 6-19
Technical Paper | Reactor | doi.org/10.13182/NT72-A31062
Articles are hosted by Taylor and Francis Online.
The sodium-bonded uranium-metal fuel elements used as driver fuel in EBR-II exhibit a characteristic fission-product release when a leak occurs in the lower part of the element. Shutting off the primary pumps at reactor shutdown reduces the effective ambient pressure, and bond sodium bearing fission-product iodine is extruded into the primary coolant by the gas in the fuel element plenum. The decay of the extruded iodine produces a surge in the xenon activity which reaches a maximum 11 or more hours after the reactor is shut down. An experimental fuel element with an intentional leak was irradiated in the reactor during several different runs so that this effect could be observed under reasonably controlled conditions. A simple model fairly well relates the size of surge to reactor power, location of the leaking element in the core, and timing of pump operation.