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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
M. Smith, Y. Zhai, G. Loesser, W. Wang, V. Udintsev, T. Giacomin, A. Khodak, D. Johnson, R. Feder, J. Klabacha,
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 407-411
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-990
Articles are hosted by Taylor and Francis Online.
The Diagnostic First Walls (DFWs) were designed to handle the plasma nuclear and radiant heating along with electro-magnetic loading induced from plasma disruptions. The DFWs also provide custom viewing apertures for the diagnostics within. Consequently, the DFWs contain numerous complex water cooling channels and are designed per ITER SDC-IC for design by analysis.
This paper presents the analyses of the Upper Port DFWs proceeding to a final design review. The finite element analyses (FEAs) performed include neutronics, radiative heating, coupled fluid dynamics and heat transfer, and static and transient structural analysis using the combined multi-physics load conditions. Static structural FEAs performed account for the dynamic amplification effects of the transient load. A detailed bolt analysis was also performed per the ITER SDC-IC bolt evaluation based on reaction loads obtained from the mechanical simulations.