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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Jun 2024
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Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
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.
R. Leonard Myatt, Nicolai N. Martovetsky, Charlotte Barbier, Kevin D. Freudenberg
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 161-167
ITER | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18072
Articles are hosted by Taylor and Francis Online.
The ITER central solenoid (CS) is wound from cable-in-conduit-conductor (CICC) and cooled by supercritical Helium (He) delivered to ~120 inner diameter (ID) turns through integrally welded "inlets." The flow to each inlet splits and passes through two pancakes, exiting at outlets. While both the He supply and return points (outlets) require penetrating the conduit wall, the inlets reside in the highest stress field, and thus become the more critical structural element.The CS Conceptual Design Review (CRD) reference He inlet design has a long, narrow slot in the inside diameter (ID) turn wall with pencil-tip shaped ends. This shape is optimized in order to minimize the hoop stress concentration. The slot length is chosen to expose each of the six superconducting (SC) sub-cables to the He cooling supply. Implementing this design at 120 inlet sites requires substantial machining and welding operations where even virgin conduit has minimal structural margin.A design space exploration produces numerous inlet options. One configuration emerges as the new reference configuration: the oblong, heavy-wall boss. It addresses all of the critical issues: bi-axial stress field, pressure drop and sub-cable flow uniformity, manufacturing costs (complexities and risks) and in-service robustness (least invasive, greatest margin).Finite element (FE) simulations are presented which highlight the results of the optimization and evaluation process.