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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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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, Suk Kwon Kim, Young-Dug Bae, Yang Il Jung, Jeong Yong Park, Yong Hwan Jeong, Byung Yoon Kim
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 165-169
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12346
Articles are hosted by Taylor and Francis Online.
For the second qualification of the blanket First Wall (FW) procurement of the International Thermonuclear Experimental Reactor (ITER), a semi-prototype of the FW has been designed with increased local surface heat flux up to 5 MW/m2. In order to investigate the fabrication procedure and methods, two types of mock-up were fabricated; one was with twelve Be tiles for high heat flux test to check the joining integrity between Be tiles and the bending Cu block and the other was for testing the thermal-hydraulic prediction by commercial code, ANSYS-CFX when it has a complex geometry such as hypervapotron, which was used for designing the semi-prototype. The former was successfully fabricated and the test conditions were obtained through the preliminary analysis with ANSYS-CFX. The later was successfully fabricated and the test with KoHLT-2 (Korea Heat Load Test facility) was performed; mass flow rate of inlet coolant was the same as the ITER condition and heat flux was loaded up to 0.65 MW/m2. The results show that the temperature of the mock-up can be predicted using the ANSYS-CFX even with the complex geometry.