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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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Blair P. Bromley
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 546-560
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-851
Articles are hosted by Taylor and Francis Online.
A study of computational/analytical neutronics and heat transfer has been carried out for different types of gas-cooled fuel bundle lattices that could be used for the sub-critical fertile/fissionable blanket of a cylindrical-geometry hybrid fusion-fission reactor (HFFR) with thorium-based fuels. The HFFR concept envisioned is one with a simple cylindrical geometry, using an anticipated variant of a magnetic mirror to confine a deuterium-tritium (DT) fusion plasma. The annular-cylindrical blanket is approximately 10 meters long and 2 meters thick, and is a repeating lattice of pressure tubes filled with 0.5-meter fuel bundles that are made of (233U,Th)O2, and refuelled continuously on-line, sharing technological features with pressure-tube heavy water reactors (PT-HWR) and the Advanced Gas-Cooled Reactor (AGR) in the U.K.. With a 2-meter thick blanket, the average fissile content in the blanket needs to be at least 2.5 wt% in order for the HFFR system to be self-sustaining in power.