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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
55th annual Nuclear News Buyers Guide now available
For American Nuclear Society members and Nuclear News subscribers, the 2024 Buyers Guide is now available in the ANS Digital Nuclear Library. The print version will be mailed along with the May “Capacity Factors/Nuclear Security” issue of Nuclear News magazine.
The corresponding ANS online Buyers Guide database is available year-round to all readers—updated with the latest products, services, and suppliers contact information for more than 600 nuclear-related companies.
Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 196 | Number 3 | March 2022 | Pages 322-341
Technical Paper | doi.org/10.1080/00295639.2021.1980361
Articles are hosted by Taylor and Francis Online.
Since nuclear power plants were first developed over 80 years ago, most have had thermal reactors with enriched uranium as the main fuel. As a result, huge amounts of depleted uranium must be stockpiled and stored. Fast reactors operating in breed-and-burn (B&B) conditions are one potential approach to reducing the need for storage facilities to hold spent nuclear fuel and maximize the effective use of uranium resources. Sustaining B&B operating conditions depends on the choice of core materials. Here, we perform neutron balance analyses to determine the best combination of fuel and coolant material. We identify the features of the reactor core needed to maintain B&B operating mode by the amount of neutron loss from the core and coolant heat removal capability. Finally, we demonstrate that a large or small sodium-cooled fast reactor core with metallic or enriched nitride fuel, respectively, can sustain the chain reaction and B&B operation mode.