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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
Kozo Gonda, Koichiro Oka, Keiichi Hayashi
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 102-108
Technical Paper | Postaccident Debris Cooling / Fuel Cycle | doi.org/10.13182/NT84-A33377
Articles are hosted by Taylor and Francis Online.
The amount and behavior of fine suspended particles and sediments in headend process vessels were investigated. Powdery fines of Zircaloy cladding, crud, and nonsoluble fission product (FP) residues were determined to be 5.3, 1.8, and 1.0 kg/ton of spent fuel reprocessed, respectively. The 1.0 kg/ton of nonsoluble FP residues and 1.8 kg/ton of crud were reasonable amounts when compared with those estimated from burnup and amount of spent fuels treated. The 5.3 kg/ton spent fuel reprocessing came from powdery fines of Zircaloy cladding that had been confirmed by chop of unirradiated Zircaloy clad tube. These residues were mostly suspended in a process solution. Particle size of sediments and suspended particles distributed mostly in <0.5-mm size. Most of the particles that arose in the dissolver scarcely settled down and passed through headend process vessels into the high-active liquid waste storage vessel, while some of the particles settled down in succession in process vessels. Uranium and plutonium dissolved well, so that they left little nonsoluble residue. The weight fraction ratio of nonsoluble plutonium to uranium was 0.05% in sediments, which was higher than the value of 0.02% in hulls. It was concluded that uranium continues to dissolve even after settling down into sediments of the dissolver.