ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
T. N. Ake, R. G. McAndrew, D. D. Whitney
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 583-586
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32802
Articles are hosted by Taylor and Francis Online.
The Babcock and Wilcox Company (B&W) normally uses part-length axial power shaping rods (APSRs) for core axial power distribution control The development and implementation by B&W and the Sacramento Municipal Utility District of a procedure for extending cycle length by removing the APSRs at the end of cycle 3 of Rancho Seco Nuclear Generating Station is explained. Increased core reactivity and hence greater cycle length were successfully achieved. Neither the reactor protection system nor normal operating limits were violated during the APSR withdrawal procedure. Further, pellet-cladding interaction was avoided, and primary coolant feedand bleed requirements were within the capacity of the plant evaporators. During the 22 h at less than full power, the average capacity factor was 81.1%, a reasonable tradeoff in light of the extension of cycle 3 by 10 effective full-power days (EFPDs). Successive use of this technique over following cycles yields average gains of 5 EFPDs per cycle.