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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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Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Fumito Okino, Laetitia Frances, David Demange, Ryuta Kasada, Satoshi Konishi
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 575-583
Technical Note | doi.org/10.1080/15361055.2017.1290972
Articles are hosted by Taylor and Francis Online.
Quantitative feasibility analysis of the tritium recovery efficiency from multiple columns of liquid PbLi droplets was conducted. Then a case study based on the HCLL specification was performed. Main concern was whether the experimentally obtained recovery efficiency from a column of droplets is applicable for the efficiency estimation from the multiple columns of droplets without any mutual degrading effects. To maintaining a safe side assumption, the tritium once released and reabsorbed on another droplet was considered to be not re-emitted while falling. By the analogy with the thermal radiation theory, the view factor which expresses the intersection ratio of radiation on another surface was applied for the estimation. The dependences on nozzle design parameters, such as nozzle pitch, number of nozzles, chamber wall clearance, and exhaust port design, were investigated. Case study results suggest that, by choosing well-suited parameters approximately 40% to 60% of the single column recovery efficiency was secured for multiple columns even on the conservative condition. The release chamber exhaust port design had a major influence. Nozzle pitch and array design have less influences, but are not negligible. However, it has to be experimentally verified to the scale-size effects and experimental programs are currently underway.