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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
Air Force issues notice to partner with Oklo on microreactor deployment in Alaska
The U.S. Department of Air Force has announced its notice of intent to award advanced nuclear technology company Oklo a contract to pilot a microreactor at Eielson Air Force Base in Alaska.
L. El-Guebaly, A. Jaber, L. Mynsberge, ARIES-ACT Team
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 582-586
Nuclear Systems: Analysis and Experiments | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19155
Articles are hosted by Taylor and Francis Online.
Just recently, the ARIES team completed the detailed design of ARIES-ACT-1 with aggressive physics and advanced SiC technology. The ability of the SiC/LiPb blanket to provide tritium self-sufficiency was among the important issues investigated in detail. To pinpoint the design elements that degrade the breeding the most, we developed a novel stepwise approach that involves building the CAD model from scratch, and, in multiple steps, adding the internals/externals of the blanket. At each step, the impact on the tritium breeding ratio (TBR) was recorded to identify the more damaging/enhancing conditions or changes to the tritium breeding. The TBR approaches 1.8 for an ideal system, and then degrades to 1.05 for the ARIES-ACT-1 reference design. This paper sheds light on several breeding-related issues that puzzled the fusion community for decades and gives insight about the impact on TBR of the individual blanket internals as well as other essential parts of the tokamak.