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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Simcha Stroes-Gascoyne, Lawrence H. Johnson, Dennis M. Sellinger
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 320-330
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33972
Articles are hosted by Taylor and Francis Online.
Safety assessment of the used fuel disposal concept requires a study of the integrity of used fuel in contact with groundwater. In this context, the initial release of 137Cs and I29I from used Canada deuterium uranium fuel segments, exposed to water at 25°C, has been studied as a function of fuel irradiation history. Percentages of inventories released after 5 days of leaching are compared to stable xenon fuel-sheath gap inventories. Cesium-137/xenon and 129I/xenon release ratios average ∼0.2 for low linear power rating (LLPR) fuel. For high linear power rating fuel, ratios are considerably larger and may approach 1. For LLPR fuel, the ratios become larger when the leaching time is increased. It is proposed that these differences are related to the microstructure of used fuel. The results indicate that the source term for the instantaneous release of isotopes of cesium and iodine should include all of the fuel-sheath gap inventory. Power history data and calculated gas release data can be used to accurately estimate the contribution of the fuel-sheath gap inventory to the source term for radionuclide release.
