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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.
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Venue, date changed for ANS’s Annual Conference
The American Nuclear Society’s 2024 Annual Conference is moving the venue in part to accommodate a higher-than-expected number of submissions for the Annual Conference and embedded topical meetings—the most received for an annual meeting in over a decade! The conference venue was changed to Mandalay Bay at the beginning of the Las Vegas strip. However, the change in accommodation comes with a change in dates: The meeting has been moved one week later than originally scheduled, to June 16–19.
Kieran Dolan, Guanyu Su, Guiqiu Zheng, Michael Ames, David Carpenter, Lin-Wen Hu
Nuclear Technology | Volume 209 | Number 4 | April 2023 | Pages 515-531
Technical Paper | doi.org/10.1080/00295450.2022.2135933
Articles are hosted by Taylor and Francis Online.
Predicting the distribution and release of tritium remains a technical challenge for advanced nuclear reactors with molten Flibe (2LiF-BeF2) salt coolants. Tritium transport models, which are currently used to forecast release behavior, are limited by uncertainty in Flibe-related tritium transport properties and by a lack of relevant benchmark experiments to test input parameters and solution methods. A new test facility has been developed at the Massachusetts Institute of Technology Research Reactor (MITR) to irradiate a molten Flibe target in an ex-core neutron beam port to further investigate tritium transport mechanisms at prototypical reactor conditions. The experiment monitored the time-dependent release of tritium from the salt-free surface and the permeation rate of tritium through the stainless steel Flibe-containing test stand. Measured results were benchmarked with a multiphysics tritium transport simulation to resolve complex effects in the test. Trends in tritium release rates from the irradiation were in agreement with the multiphysics simulation of the test, which combined computational fluid dynamics, radiative heat transfer in participating media, and tritium transport in STAR-CCM+.