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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.
O. Kazachenko, B. Bornschein, N. Kernert, L. Doerr, M. Glugla, V. Weber, D. Stern
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 67-70
Technical Paper | Iter and Fusion | doi.org/10.13182/FST08-A1766
Articles are hosted by Taylor and Francis Online.
The design of a tritium processing loop for KATRIN tritium source and results of test set-up operation are presented. The constant source intensity is supported by high purity (> 95% of tritium) of tritium circulated through the source with 4.110-4 g/s rate. The possibility of source parameters stabilization was verified with test facility "TILO" which was built for this purpose. The long term (30 days) deuterium circulation with flow rate 0.2 Pa m3/s shows that using of standard high accuracy pressure sensors from MKS and NI control electronics allows to stabilize the flow rate in the system with 0.1% accuracy. The reliability of process equipment was tested as well during about 3000 h of TILO operation.