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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.
R. L. Currie, P. B. Parks, J. L. Jarriel
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 356-362
Technical Paper | Reactor | doi.org/10.13182/NT71-A30984
Articles are hosted by Taylor and Francis Online.
Subcritical multiplication constants have been derived from static and pulsed measurements for arrays of large, hollow cylinders of uranium-aluminum alloy. The cylinders were of two types: 11.21-cm-i.d., 20.07-cm-o.d. bare 235U-Al alloy castings and 10.07-cm-i.d., 12.27-cm-o.d. Alclad “logs” extruded from the castings. The alloy was 9.985 wt% enriched uranium (92.2% 235U) in aluminum. These measurements extended previous benchmark experiments with small diameter rods of lower enrichment into the region of larger diameters and higher enrichments. The transport diffusion theory codes MGBS-TGAN overestimated the values of keff for the arrays tested by 7 to 12%. The more sophisticated Monte Carlo code KENO was more accurate, with errors less than 5%.
