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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.
Felix Schreiner, Sherman Fried, Arnold M. Friedman
Nuclear Technology | Volume 59 | Number 3 | December 1982 | Pages 429-438
Technical Paper | The Backfill as an Engineered Barrier for Radioactive Waste Management / Radioactive Waste Management | doi.org/10.13182/NT82-A33001
Articles are hosted by Taylor and Francis Online.
The mobility of cationic neptunium, plutonium, americium, and sodium, and of the anionic species pertechnetate, , has been determined in samples of various sediments from the ocean floor, and in bentonite and hectorite clay. The experiments were conducted at ambient temperatures (298 ± 5 K), and the periods of observation ranged from several hours to ten months. All tests were carried out under static conditions permitting only molecular diffusion of the ionic species. Results indicate very low mobilities for the transuranium elements plutonium and americium, for which the upper limit of the effective diffusion coefficient is <10−10 cm2 · s−1. Sodium, neptunium, and were found to have higher mobilities characterized by values for the effective diffusion coefficient of 3 × 10−6, 1.8 × 10−8, and 3.2 × 10−6 cm2 · s−1, respectively. Some implications of the measured results for the assessment of barrier effectiveness are discussed.