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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
Yigal Ronen, Samuel Carmona
Nuclear Science and Engineering | Volume 74 | Number 2 | May 1980 | Pages 84-94
Technical Paper | doi.org/10.13182/NSE80-A19625
Articles are hosted by Taylor and Francis Online.
Water breeder reactors based on thermal water reactors have the advantages of a well-proven technology, a wide operational experience, and an acceptable safety status, the latter from using water as a coolant and having a negative void coefficient. Water breeder reactors are now in operation for the 232Th-233U cycle and are being designed for the 238U-Pu cycle. This paper proposes a water breeder system in which two reactors operate in symbiosis, one using 238U-233U as fuel and producing plutonium, and the other using 232Th-Pu as fuel and producing 233U. Thus, each reactor feeds the other. From the breeding point of view, the combined system has an advantage over the separate 238U-Pu and 233Th-233U cycles.