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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
A. N. Perevezentsev, L. A. Bernstein, L. A. Rivkis, I. G. Prykina, V. V. Aleksandrov, I. A. Ionessian, M. I. Belyakov, I. B. Kuprianov
Fusion Science and Technology | Volume 72 | Number 1 | July 2017 | Pages 1-16
Technical Paper | doi.org/10.1080/15361055.2016.1273659
Articles are hosted by Taylor and Francis Online.
The subject of this study is the evaluation of tritium outgassing and removal from metals such as tungsten, beryllium, stainless steel, and copper alloy. In addition, a composite sample assembled from tungsten, copper alloy, and stainless steel was also studied. Samples of individual materials and composite samples were of thicknesses and compositions representing the internal components of the ITER vacuum vessel. The samples of materials were loaded with tritium by exposure to a gaseous tritium-deuterium mixture (about 1:1) at a temperature of 473 K and a pressure of about 0.05 MPa. The rate of outgassing was measured at temperatures of about 295, 308, and 323 K under static or dynamic atmospheres either of ambient air or dry air or argon. The study allows recommendation of conditions for storage of in-vessel components and reduction of the rate of tritium outgassing. The metals’ samples were also subject to study of tritium removal by thermal desorption under purge with argon containing 5 vol % of hydrogen. The study has demonstrated that this detritiation procedure allows for removal of large portions of the tritium inventory and substantial reduction in tritium outgassing rates.