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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Reviewers needed for NRC research proposals
The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
Yury A. Bezrukov, Sergey A. Logvinov, Vladimir N. Ul'yanovsky, Nikolay A. Strebnev
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 122-130
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3492
Articles are hosted by Taylor and Francis Online.
In this paper, results of experimental studies of the coolant flow mixing at different boron concentration and different temperature in the VVER-1000 reactor downcomer and lower plenum are presented. Studies concerning boron dilution were carried out on the reactor model in scale 1:5 for cases of reactor coolant pump (RCP) startup and resumption of natural circulation during a small-break loss-of-coolant accident. It has been shown that for RCP startup, the effect of Reynolds number on mixing is negligible. Studies of flow mixing in the reactor downcomer were carried out applied to emergency core cooling system water injection into the cold loop leg and reactor downcomer. Results of the tests on model and reactor have been analyzed, and recommendations for calculations have been provided.