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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.
H. C. Burkholder, M. O. Cloninger, D. A. Baker, G. Jansen
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 202-217
Technical Paper | Radioactive Waste | doi.org/10.13182/NT76-A31683
Articles are hosted by Taylor and Francis Online.
The safety incentives for separating and eliminating various elements from high-level radioactive waste prior to final geologic isolation have been examined. The study required evaluation of numerous parameters concerning the transport of radioactivity from the geologic isolation repository to humans. Available data were used whenever possible, but many of the study parameters had to be estimated. The values used were either consistent with current knowledge or were selected to maximize the calculated potential radiation doses. Thus, incentives for removing various elements from the waste were greatly increased. Also, incentives were greatly overestimated by neglecting all short-term risks and by assuming that elements removed from the waste could be eliminated from the earth without risk. Despite these conservative assumptions, the study found that for reasonable isolation conditions, the potential incremental radiation doses would be of the same order as or less than doses from natural sources. Although not a comprehensive evaluation or partitioning incentives, the study does show that incentives for removal of any elements, including the transurardcs, from high-level waste do not exist for the situations investigated. The methods developed for this study can be applied to evaluate any combination of waste type and geologic medium at sites that are candidates for the isolation of nuclear waste materials.