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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
T. G. Broughton, P. S. Walsh
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 217-225
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Fission Reactor | doi.org/10.13182/NT81-A32626
Articles are hosted by Taylor and Francis Online.
A method has been developed to aid pressurized water reactor (PWR) power plant operators in monitoring the transition of the plant from normal full-power conditions to expected post-reactor-trip conditions. Using a pressure-temperature plot or display, the operator can determine in real time whether the transition is normal or if a fault has occurred that has caused a loss of adequate reactor coolant system saturation margin, a loss of reactor coolant system heat sink, or excessive cooldown of the reactor coolant system. The method allows rapid differentiation among these faults and also has the capability of detecting multiple abnormalities. Evaluations of the technique have been performed with operators using manual plots in a classroom environment plotting data from plant transients and computer simulations. This method uses information that is currently available in PWR control rooms and that can be displayed on a cathode ray tube in the required format for analysis. This method appears to be very effective in communicating plant status to operators during a post-reactor-trip condition; application to other plant conditions is being investigated.