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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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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.
Robert E. Einziger, Bobby R. Seidel
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 25-39
Technical Paper | Fuel | doi.org/10.13182/NT80-A17067
Articles are hosted by Taylor and Francis Online.
The Experimental Breeder Reactor II Mark-II metallic-driver-fuel element has been irradiated to high burnup to assess element lifetime and performance reliability. The elements breached at 10 at.% burnup or greater. This increase in burnup potential compared to its predecessor, the Mark-IA (limited to a burnup of 3 at.%), is due to the reduction of fuel-cladding mechanical interaction (FCMI) resulting from the smaller smear density, a lower fission-gas-induced cladding stress resulting from the increased plenum volume and increased cladding thickness, and a reduction in fuel-cladding chemical interaction (FCCI) due to a change in cladding material. The cladding breach in the solution-annealed Type 316 stainless-steel-clad elements was in the restrainer dimple located above the original fuel column, not in the upper half of the fuel column as in the Type 304L stainless-steel-clad elements. During irradiation, the prime cause of cladding deformation was swelling. Due to the extensive release of fission gas after interconnected porosity developed, the fuel deformation was restricted by the cladding. After fuel-cladding contact, a small amount of FCCI, as predicted by out-of-pile measurements, occurred, but little FCMI is thought to have taken place.