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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
S. Chatzidakis, A. Ikonomopoulos, M. Alamaniotis
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 392-406
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14171
Articles are hosted by Taylor and Francis Online.
A systematic approach for performing a holistic reactivity insertion analysis in research reactors using the RELAP5/MOD3 code is proposed. The intention is to demonstrate, in an orderly manner, a method for determining the limiting reactivity insertion in a research reactor facility. Indispensable constituents of the algorithmic approach are the introduction of the "time-to-failure" parameter, the selection of the reactivity insertion duration, the evaluation of the control rod drop time, and the computation of engineering factors. The methodology is demonstrated through a RELAP5/MOD3 parametric study performed to determine the limiting reactivity insertion values for the Greek Research Reactor-1 (GRR-1). In the framework of this study, the core nodalization effect on reactivity limits and the degree of conservatism introduced by the engineering factors are discussed. The results obtained confirm the applicability of the approach and reveal the effect of the parameters mentioned above on the performance of reactivity insertion analysis.