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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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Fusion Science and Technology
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.
Asashi Kitaioto, Mitsuhiro Ohta
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 971-976
Material; Storage and Processing | doi.org/10.13182/FST92-A29877
Articles are hosted by Taylor and Francis Online.
The separation performance of tritium by the thermal diffusion method with low inventory was simulated as an alternative method to the cryogenic distillation in Fusion Fuel Cycle. The separation performance of thermal diffusion method was evaluated by the ternary transport equations with isotope exchange reaction. The results for HT - H2 system, show the isotope exchange reaction, H2 + T2 = 2HT, plays an important role in the separation performance of tritium, even in a tracer level of tritium.
