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Division Spotlight
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.
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.
J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, G. Poullot
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 148-157
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32540
Articles are hosted by Taylor and Francis Online.
The Nuclear Safety Department of the French Commissariat à l’Energie Atomique has achieved an important experimental program relating to the criticality of 4.75-wt%-235U-enriched UO2 rods in water with various configurations. Two steps of this program are set out. The first one consisted of doing the parametric study of regular lattices of rods in a sodium nitrate solution (study connected with the problems raised by the dissolution of irradiated elements). The results obtained show the poisoning effect due to the nitrate ion at various concentrations. The second step concerns the study of the effect due to the interpositioning of hydrogenous materials between four 18 × 18 assemblies at 13.5-mm square pitch (study connected with the problems raised by the accidental sprinkling of a mist into a fuel storage). The results obtained allow one to determine the optimum theoretical moderation conditions for the storage of new fuel elements. In all cases the theoretical results are in good agreement with experimental results.