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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.
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.
Harry Farrar, IV, W. N. McElroy, E. P. Lippincott
Nuclear Technology | Volume 25 | Number 2 | February 1975 | Pages 305-329
Technical Paper | Material Dosimetry | doi.org/10.13182/NT75-A24371
Articles are hosted by Taylor and Francis Online.
Measurements have been made of the helium generated by (n,α) reactions in boron that have resulted from several fast-neutron irradiations in the Experimental Breeder Reactor II (EBR-II) and the Coupled Fast Reactivity Measurements Facility (CFRMF). The neutron environments were characterized using multiple-foil dosimetry and reactor physics calculations. Precise helium determinations of boron specimens in milligram size were made using a high-sensitivity-gas mass spectrometer system specifically designed for this purpose. Spectrum-integrated helium -production cross sections have been determined from the measured helium concentration data and the experimentally measured values of total neutron flux. Good consistency has been found between the measured reaction rates of10B and 235 U. In the case of certain other dosimetry foils where cross sections are less accurately known, inconsistencies of up to 30% in predicted reaction rates have been found in EBR-II neutron spectra perturbed by the presence of B4C. This indicates that the 10B(n,α)7reaction is a very useful addition to multiple-foil dosimetry sets, and that its use will help to establish more accurate cross-section data for other foil reactions.