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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
T.V. Kulsartov, Y.V. Chikhray, I.L. Tazhibaeva, V.P. Shestakov
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 919-923
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963730
Articles are hosted by Taylor and Francis Online.
Be-copper alloy duplex structures are planed to be used as the structural material of the first wall for ITER. CuCr1Zr0.1 copper alloy is one of the prospective components of such structures. To ensure safety and to solve ecological problems concerning fusion reactor operation it is necessary to have estimations of tritium inventory in the copper alloy CuCr1Zr0.1 and in Be-copper alloy duplex structures.
In this work the results of the following experiments on determination of hydrogen permeation parameters are presented:
• Investigation of hydrogen permeation for beryllium-copper duplex structure. Experiments were carried out in the temperature range from 873 K to 1023 K, at input hydrogen pressures between 102 Pa and 103 Pa.
• Investigation of hydrogen permeation for copper alloy CuCr1Zr0.1 in the temperature range from 723 K to 973 K, at input pressures of hydrogen between 102 and 103 Pa and for samples with different thickness.
