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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
Nuclear and Emerging Technologies for Space (NETS 2025)
May 4–8, 2025
Huntsville, AL|Huntsville Marriott and the Space & Rocket Center
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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June 2025
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May 2025
Latest News
Delivering new nuclear on time, the first time
Mark Rinehart
The nuclear industry is entering a period of renewed urgency, driven by the need for stable baseload power, heightened energy security concerns, and expanded defense infrastructure. Now more than ever, we must deliver new nuclear projects on time and on budget to maintain public trust and industry momentum.
The importance of execution certainty cannot be overstated—public trust, industry investment, and future deployment all hinge on our ability to deliver these projects successfully. However, history has shown that cost overruns and schedule delays have eroded confidence in the industry’s ability to deliver nuclear construction. As we embark on many first-of-a-kind (FOAK) reactor builds, fuel cycle infrastructure projects, and extensive defense-related nuclear projects, we must ensure that execution certainty is no longer an aspiration—it is an expectation.
T. Yokomine, S. Ebara, A. Shimizu
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 267-272
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8913
Articles are hosted by Taylor and Francis Online.
The purpose of the High Flux Test Module (HFTM) in International Fusion Material Irradiation Facility (IFMIF) is to irradiate material specimens to a very high fluence (DEMO relevant ones) in a very few years. In IFMIF-EVEDA which is selected as one of the broader approach activities, the reference solution for the assemblies is a vertical set-up (EU); an alternative horizontal solution, H-HFTM (Japan), which could become very useful for very high temperature tests, is also part of this work. This paper presents the overview of H-HFTM and reports on the recent Japan activities for H-HFTM in the IFMIF-EVEDA framework.