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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.
B. F. Myers, N. L. Baldwin, W. E. Bell
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 501-508
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31910
Articles are hosted by Taylor and Francis Online.
A review and analysis of available data on the release of fission gases from high-temperature gas-cooled reactor fuel particles indicates that the release of short-lived nuclides (half-life ≲5.3 days) occurs from the fissile material primarily by a mechanism involving recoil followed by gas-phase and bulk diffusion in the surrounding material at temperatures up to at least 1300°C (1573 K). The gas-phase contribution to the release of short-lived nuclides is dominant at temperatures below 600°C (873 K), and bulk diffusion is dominant at temperatures above 900°C (1173 K). Fission gas release to birth ratio (R/B) varies with half-life to a power of ∼0.2 at 300°C (573 K) and ∼0.5 at 1100°C (1373 K). For the short-lived isotopes, R/B is independent of burnup over the range from 0 to 63% FIMA in UC2 kernels; for dense ThO2 kernels, the data are insufficient to determine the burnup dependence. For the long-lived and stable isotopes, release from dense ThO2 kernels is strongly dependent on burnup. Iodine and tellurium isotopes may be treated as if they were xenon isotopes.