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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
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
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
Charles C. Price, Howard A. Larson, Robert N. Curran, John I. Sackett
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 272-284
Technical Paper | Analyse | doi.org/10.13182/NT82-A26290
Articles are hosted by Taylor and Francis Online.
A measurement of water flow on the Experimental Breeder Reactor II (EBR-II) evaporator down-comers, a measurement of sodium flow on the EBR-II secondary sodium system, and a calibration experiment at the University of Utah Water Research Laboratory are three experiments using the pulsed neutron activation (PNA) technique to determine flow rate. The EBR-II data permit calculation of flow rates and comparisons with instrumentation and the Water Research Laboratory data permit investigation of different weighting schemes for determining the flow rates. The PNA technique is an accurate and convenient procedure that yields flow rates without accompanying system disturbance. Pipe size is not a factor except that corrections may be needed for asymmetry of larger pipes. Accuracy is adequate for most applications and indicates the PNA technique is most useful as a calibration device.
