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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
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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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.
Zongbiao Ye, Wenyao Yang, Lei Shu, Zhijun Wang, Qiancheng Liu, Qiang Yan, Jianjun Wei, Kun Zhang, Fujun Gou
Fusion Science and Technology | Volume 76 | Number 2 | February 2020 | Pages 157-162
Technical Paper | doi.org/10.1080/15361055.2019.1704596
Articles are hosted by Taylor and Francis Online.
The corrosion behavior of Type 316L stainless steel in stagnating liquid Li under an elevated-temperature environment was investigated using a scanning electron microscope and an energy dispersive X-ray detector and self-designed laser-induced breakdown spectroscopy. A nonuniform and cell-like branched structure separated by distinct boundaries was observed, and a porous and rugged corroded layer was formed on the surface of the substrate after 500 h exposing 350°C liquid Li. This showed that the intensity of the Cr element on the superficial corroded sample decreased significantly when the depth reached ~2.8 μm and then was gradually restored in the range of ~5.6 μm. Meanwhile, the intensity of the Li element revealed consistent reduction to zero at ~4.0 μm. This study disclosed element transfer and penetration along a depth in the corrosion process between the liquid lithium and steel matrix.