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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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Luis E. Herranz, Jesús Polo
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 168-176
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34973
Articles are hosted by Taylor and Francis Online.
The significance of iodine for source term quantification has been studied by investigating its chemical behavior under the prototypical conditions of a hypothetical severe accident within the containment. As a result, some computer codes were developed and their validation is currently under way. The loss-of-fluid test (LOFT) program was one of the most relevant research projects in the area of nuclear safety. Its last experiment, LP-FP-2, simulated a V-sequence. A great deal of information was recorded on the fission product release, transport, and deposition. A theoretical approach to the chemical behavior of iodine in the blowdown suppression tank (BST) of the LOFT facility was attempted with the IODE and IMPAIR-2/M codes. The comparison of the predictions with the existing experimental data led to the conclusion that the BST system behaved as a low-volatility system, with most of the iodine in the form of the soluble nonvolatile species iodide. Only a partial conversion to volatile molecular iodine was observed due to the presence of radiation. However, the intensity of the γ field was so weak that this transformation was not quantitatively meaningful.