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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Taewoo Tak, Deokjung Lee, T. K. Kim
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 427-435
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A19430
Articles are hosted by Taylor and Francis Online.
A new design of ultralong-cycle fast reactor (UCFR) with power rate of 1000 MW(electric) has been developed based on the strategy of breed and burn. The bottom region of the core with low-enriched uranium plays a role of igniter of the core burning and the upper natural uranium region acts as a blanket for breeding. Fissile materials are bred in the blanket and the active core moves upward at a speed of 5.0 cm/year. Through the core depletion calculation using Monte Carlo code McCARD, it is confirmed that a full-power operation of 60 years without refueling is feasible with respect to nuclear isotopics and criticality. Core performance characteristics have been evaluated in terms of axial/radial power shapes, reactivity feedback coefficients, etc. This design will serve as a base model for further design study of UCFRs using light water reactor spent fuels in the blanket region.