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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. A. Parish, J. W. Davidson
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 324-342
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32436
Articles are hosted by Taylor and Francis Online.
A waste management concept that employs irradiation of fission products in fusion reactor blankets is evaluated. The purpose of the irradiation is to reduce the toxicity of the material to be committed to geologic disposal Target isotopes included 90Sr, 137Cs, 129I, 99Tc, 135Cs, and 93Zr. The (n,γ), (n,2n), (n,3n), (n,p), (n,α), (n,d), (n,t), and (n,n'α) reactions were all considered to contribute to the transmutation process. Extensive chains were employed in the depletion calculations performed to quantify the toxicity of the products. A sharp reduction in the shortterm toxicity of the fission wastes could not.be accomplished due to the small capture cross sections of 90Sr and 137Cs and limitations on the neutron flux. Reduction in the long-term toxicity by a factor of 100 or more appears achievable, but should not be pursued unless the toxicity of the actinide wastes can also be substantially reduced.