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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
L. V. Boccaccini
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 615-622
Test Blanket, Fuel Cycle, and Breeding | 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-A19160
Articles are hosted by Taylor and Francis Online.
In the last years EU started a new effort for the definition of a Roadmap for the fusion beyond ITER up to the construction of the DEMO reactor. The blanket technology, key issue for the development of the fusion breeder reactor, is an important part of this review. In the last 10 years the R&D of EU in blanket has been focused on two kinds of blanket concepts, namely the Helium Cooled Pebble Bed (HCPB) and Lithium lead (HCLL); both are EU reference concepts for DEMO and for the test in ITER. In addition to these two reference concepts, few other concepts have been investigated in EU. One of these is the Dual Coolant Lithium Lead (DCLL) that was developed in the 90-ties in Karlsruhe and UCSD. The spectrum of blankets studied in EU includes also a water cooled blanket with liquid breeder, the WCLL.