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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
F. Bonelli, L. V. Boccaccini, B.-E. Ghidersa, Q. Kang, L. Savoldi, R. Zanino
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 507-511
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-985
Articles are hosted by Taylor and Francis Online.
The first 3D thermal-fluid-dynamic and structural analyses done for the design and pre-test assessment of the so-called Thermo-Cycle Mock-up (TCM), reproducing about 0.3 m2 of a flat first wall (FW) with relevant helium cooling channels, are presented, based also on previous computational and experimental activities conducted at KIT but limited so far to a single cooling channel with straight heated length. The TCM is the first of a series of FW mock-ups presently under construction, to be tested starting from 2015 in the large HELOKA facility at KIT. Here, the fluid dynamics in the 180° turns of the TCM cooling channels is investigated together with the effects of heat transfer between neighboring channels, when the plate is subject to steady-state heat fluxes in the range 0.3-0.5 MW/m2. Based on the computed temperature maps, the stresses in the TCM and the related damage figures for the main failure modes (i.e., ratcheting and creep/fatigue) are assessed. These are compared with allowable limits in code and standards for the qualification of the TCM design and related to the prediction of the behavior of the component in the actual fusion environment.