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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
Udo K. Wehmann
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 277-282
Technical Paper | doi.org/10.13182/NSE88-A29041
Articles are hosted by Taylor and Francis Online.
This paper describes the main characteristics of the core of the SNR-2 fast breeder reactor (FBR), which is being planned within the European collaboration on FBRs. Core design aspects are then discussed. Fuel element management with an inward shuffling after each cycle is illustrated, which offers advantages with respect to linear rating, steel damage, and average discharge burnup. The full three-dimensional power and burnup history has been calculated and some typical results are presented. The shutdown requirements and the capabilities of the two shutdown systems of SNR-2 are discussed. The need for a reliable surveillance of the power distribution is demonstrated by the pronounced power tilts in case of unintentional withdrawal of an absorber rod. Finally, a short review of the main nuclear design methods and their validation with the help of the evaluation of experiments in zero-power facilities and power reactors is given.