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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Cheng-Wei Wu, Douglass L. Henderson, Edgar F. Bennett
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 235-255
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A35032
Articles are hosted by Taylor and Francis Online.
An innovative liquid-metal reactor, the Integral Fast Reactor (IFR), is being developed at Argonne National Laboratory. One characteristic of the IFR is the fuel cycle closure. Fissile material bred and fissionable material produced in the reactor are recycled back into the reactor. Waste generated during fuel reprocessing will be packaged into special waste canisters and will be shipped to a repository for final disposal. Prior to its removal from the facility, a measurement of the fissile content will be necessary as a part of an overall fissile material inventory accountability system. A particular form of nondestructive assay called delayed neutron nondestructive assay (DNNDA) is being developed to assist in the establishment of an accountability system. A preliminary neutronics investigation for the current DNNDA has been made to assist and verify the characteristics of the design from a neutronic aspect. A 1011 n/s, 14-MeV neutron source would provide adequate counting statistics for fissile material at the milligram to gram level.
