ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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!
Latest Magazine Issues
Sep 2023
Jul 2023
Latest Journal Issues
Nuclear Science and Engineering
October 2023
Nuclear Technology
Fusion Science and Technology
Latest News
National Museum of Nuclear Science and History explores “atomic” culture
For many of us, the toys of our childhood leave indelible marks on our consciousness, affecting our long-term perceptions and attitudes about certain things. Hot Wheels may inspire a lifelong fascination with fast, flashy automobiles, while Barbies might shape ideas about beauty and self-image. For the generation who grew up during the Atomic Age—the post–World War II era from roughly the mid-1940s to the early 1960s—the toys, games, and entertainment of their childhoods might have included things like atomic pistols, atomic trains, rings with tiny amounts of radioactive elements, and comic books, puzzles, and music about nuclear weapons.
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+.