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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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.
Enrico Lorenzini, Pier Giacomo Sola, Marco Spiga
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 180-184
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33314
Articles are hosted by Taylor and Francis Online.
A simple model is applied for the analysis of radiative heat transfer in a pressurized water reactor fuel assembly during steady state and under a loss-of-coolant accident. The method includes a matrix calculation of view factors, performed dividing the bundle into unit cells composed by portions of fuel rods and by a coolant subchannel. The cells are correlated considering imaginary faces among them, and the pertinent equations are simultaneously solved for the whole assembly. Some results are related for various values of the heat flux in different operational and accidental conditions.
