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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.
P. Barbucci, G. Mariotti, N. Cerullo, P. Riscossa+ A. Cesana, M. Terrani, G. Sandrelli
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 467-478
Technical Paper | doi.org/10.13182/NSE88-A23580
Articles are hosted by Taylor and Francis Online.
An analysis of the neutron transport in the region around the Caorso [a 2600-MW(thermal) boiling water reactor] reactor pressure vessel and the streaming through three penetrations of the sacrificial shield, located at various distances from the reactor core midplane, was performed. The DOT 4.2 and MORSE codes were used to evaluate the neutron flux levels and spectra in several locations, some of which are very far from the neutron source. The calculational methodology used for this analysis is described, and the results are compared with those of some measurements carried out at the Caorso power station during the second cycle of operation using the multiple foil activation technique. A comparison shows that the agreement is good from both the neutron total flux and energy distribution points of view. Possible reasons for some observed discrepancies are discussed.