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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.