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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.
Yoshiaki Oka, Ichiroh Yanagisawa, Shigehiro
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 642-655
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT81-A32809
Articles are hosted by Taylor and Francis Online.
A design study of the neutron irradiation facility for boron neutron capture therapy was performed using two-dimensional transport calculations. Dosedepth distributions in a phantom head were calculated for various neutron energies. The epithermal neutrons having the energies between 10 eV and 0.5 keV are suitable for the therapy. To obtain the epithermal neutron beam, the neutrons leaking downward through the central hole of the annular core TRIGA reactor were moderated through a mixture of heavy water with aluminum whose volume ratio is 15:85. Bismuth and lithium fluoride tile was used to remove gamma rays and thermal neutrons from the beam. Iron, borated polyethylene, and lead were used as the shield surrounding the moderation layer. When the epithermal neutron column is used, the maximum usable depth and irradiation time are 6.9 cm and 7.25 h, respectively, at a 2-MW level.