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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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.