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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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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Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
Takeshi Matsuoka, Michiyuki Kobayashi
Nuclear Science and Engineering | Volume 98 | Number 1 | January 1988 | Pages 64-78
Technical Paper | doi.org/10.13182/NSE88-A23526
Articles are hosted by Taylor and Francis Online.
A reliability analysis methodology, GO-FLOW, is presented. Detailed explanations and two examples of GO-FLOW analysis are given. The GO-FLOW is a success-oriented system analysis technique. The modeling technique produces the GO-FLOW chart, which is composed of operators and signal lines and represents a function of the system. A signal does not represent a “change of condition” but some physical quantity or information. The intensity of a signal represents the probability of actual or potential existence of a physical quantity, the probability that some information exists, or a time interval between two successive time points. The examples of analysis show the applicability of the GO-FLOW method to a phased mission problem (a boiling water reactor emergency core cooling system) and to a time-dependent unavailability analysis (a pressurized water reactor auxiliary feedwater system). The GO-FLOW has proved to be a valuable and useful tool for system reliability analysis.