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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.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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
Hanford completes wastewater basin work to support tank waste treatment
Record-breaking heat and the vast size of the job did not stop the Department of Energy’s Office of River Protection and its tank operations contractor, Washington River Protection Solutions (WRPS), from completing a construction project critical to the Hanford Site’s Direct-Feed Low-Activity Waste program for treating radioactive tank waste.
Y. Zhai, G. Loesser, M. Smith, W. Wang, V. Udintsev, T. Giacomin, A. Khodak, D. Johnson, R. Feder
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 526-530
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-103
Articles are hosted by Taylor and Francis Online.
ITER diagnostic first walls (DFWs) and diagnostic shield modules (DSMs) inside the port plugs (PPs) are designed to protect diagnostic instrument and components from a harsh plasma environment and provide structural support while allowing for diagnostic access to the plasma. The design of DFWs and DSMs are driven by 1) plasma radiation and nuclear heating during normal operation 2) electromagnetic loads during plasma events and associate component structural responses. A multi-physics engineering analysis protocol for the design has been established at Princeton Plasma Physics Laboratory and it was used for the design of ITER DFWs and DSMs. The analyses were performed to address challenging design issues based on resultant stresses and deflections of the DFW-DSM-PP assembly for the main load cases. ITER Structural Design Criteria for In-Vessel Components (SDC-IC) required for design by analysis and three major issues driving the mechanical design of ITER DFWs are discussed. The general guidelines for the DSM design have been established as a result of design parametric studies.