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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.
K. G. Porges
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 194-196
Technical Note | Instrument | doi.org/10.13182/NT72-A31135
Articles are hosted by Taylor and Francis Online.
Certain reactor safety instrument channels require the assured detection of weak neutron bursts in the presence of strong gamma background. Inasmuch as the importance of some such channel justifies a fairly elaborate detection system, neutron multiplication suggests itself as a means of enhancing the signal strength relative to the background. While such a system may be technically feasible, it is subject to severe limitations inherent in the statistical nature of multiplication, which are explored in this Note. In particular, it is shown that, given a reasonably high intrinsic neutron detection efficiency, the statistical quality of detection is optimized for relatively weak multiplication factors and worsens again as multiplication increases. The overall design of a multiplying detection system is in fact a matter of considerable complexity since multiplication affects source geometry and energy distribution as well as statistics. A potential application is the detection of fuel failures in a liquid metal fast breeder reactor (LMFBR) plant by monitoring the coolant flow system for delayed neutrons downstream from the core.