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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Robert Kozma, Masaharu Kitamura, J. Eduard Hoogenboom
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 242-253
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35365
Articles are hosted by Taylor and Francis Online.
The binomial theory of void fraction fluctuations is applied to the interpretation of neutron detector signals generated by density fluctuations of the coolant in nuclear reactors. Experiments are performed at the experimental setup for noise investigations on boiling effects (NIOBE) with the injection of nitrogen bubbles into a narrow coolant channel. NIOBE is a thermal-hydraulic loop located in the Higher Educational Reactor (Hoger Onderwijs Reactor) of the Interfaculty Reactor Institute, Delft, The Netherlands. The monitored two-phase-flow parameters include the size of bubbles and the density of bubble populations within the field of view of the neutron detectors, as well as local void fraction. Based on the experiments, a quantitative relationship is established between the parameters of two-phase flows and the measured neutron noise intensity. The validity of the results is not restricted to research reactor applications, and the conclusions can be used to monitor two-phase-flow coolant in power reactors as well.