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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.
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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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.
Dong Won Lee et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 48-51
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8874
Articles are hosted by Taylor and Francis Online.
In order to verify the integrity of the first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) the fabricated Be/Cu mock-ups were tested at the TSEFEY, e-beam facility, in Efremov, Russia. The Be/Cu mock-ups were joined with CuCrZr for a heat sink material among the Cu alloys and 316L austenitic stainless steel (SS316L) tubes for a coolant and then, joined with Be tiles for an armor material. Hot Isostatic Pressing (HIP) was used as a manufacturing method at 1050 °C, 100 MPa for 2 hours for a Cu/SS joining and at 620 °C, 100 MPa for 2 hours for a Be/Cu joining. The high heat flux (HHF) tests were performed for two Be/Cu mock-ups with a 2.5 MW/m2 heat flux and 80 sec durations, which were determined from a preliminary analysis with ANSYS-11. The temperature results from the test showed a good agreement with the analysis results and the fatigue lifetime was evaluated from the strain analysis results.