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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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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.
J. W. Kormuth
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 99-102
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31976
Articles are hosted by Taylor and Francis Online.
Westinghouse pressurized water reactors have experienced soluble releases of 58Co and natural 58Ni into the reactor coolant during refueling shutdowns. When the soluble inventory of 58Co was not managed properly, the refueling water became contaminated, forcing delays in refueling operation schedules. Subsequent testing at other refueling shutdowns identified the development of oxygen species in the coolant as the prime reactant causing the dissolution. Hydrogen peroxide addition to reactor coolant under prescribed conditions was successfully used to create a controllable and soluble release of 58Co and nickel. The controlled release permitted a more deliberate removal of the activity by ion-exchange purification. A lesser, soluble release of the activity was shown to be caused by the depression in reactor coolant pH resulting from dissociation of boric acid following reactor coolant system boration and cooldown.