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Division Spotlight
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.
Meeting Spotlight
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Michael G. Izenson, Javier A. Valenzuela
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1828-1834
Plasma-Facing Component | doi.org/10.13182/FST92-A29984
Articles are hosted by Taylor and Francis Online.
Helium cooling offers safety advantages for fusion reactors because helium is single-phase and chemically inert. The Normal Flow Heat Exchanger (NFHX) enables highly efficient heat transfer to helium with low pressure drops at high heat fluxes. Thus, the NFHX enables helium cooling of divertor panels in Tokamak reactors and potentially enhances the safety of fusion power production. This paper explains the NFHX concept, presents the current status of the technology, and shows how the NFHX can be used to cool divertor panels in Tokamak reactors.
