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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
N. R. Chellew, W. E. Miller, R. W. Kessie, C. C. McPheeters, P. A. Nelson
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 125-132
Technical Paper | Instrument | doi.org/10.13182/NT74-A31368
Articles are hosted by Taylor and Francis Online.
Work has been completed to demonstrate the feasibility of a new cladding-failure monitoring technique based on determination of the 135I content of the primary sodium coolant of Liquid Metal Fast Breeder Reactors (LMFBRs). The method was devised to aid in detecting the penetration of fuel element cladding by sodium coolant. The method consists of isolating a small volume of primary sodium, sparging it with an inert gas to strip out dissolved gases which are discarded, further sparging the sample to strip 135mXe produced by 135I decay, and calculating the 135I content of the sodium from the 135mXe content of the second sparge. A sparging monitor was built and tested to determine the time required to sparge dissolved radioxenon (133Xe) from molten sodium. This time varied from ∼1 to 1.5 min, depending on experimental conditions. For the calculated background level of 135I in the primary sodium of Experimental Breeder Reactor II, a counting time of ∼2 min would be required to determine the amount of 135mXe removed by the second sparging to a 1σ counting precision of ±4%. A shorter counting time would be required for higher 135mXe levels that would occur during fuel failure. A system with automatic controls was designed for monitoring 135I in the primary sodium of an LMFBR.