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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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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.
A. Abou-Sena, A. Ying, M. Youssef, M. Abdou
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 211-215
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8904
Articles are hosted by Taylor and Francis Online.
The Quarter Port Submodule (QPS) was proposed as a Solid Breeder (SB) Test Blanket Module under the US program of the SB blankets. The QPS features layer configuration, in its left half, where the SB pebble beds are parallel to the first wall and edge-on configuration, in its right half, where the SB pebble beds are perpendicular to the first wall. The objective of this study is to investigate: (i) the QPS thermal profile under steady state conditions and ITER transient loads, and (ii) the impact of the interface conductance h on the QPS thermal profile. In addition the effect of lack of contact, at the SB pebbles/structure interface, on the QPS thermal profile is presented. The results of the steady state cases showed that h has a significant impact on the QPS thermal profile. The QPS transient analysis provided results on: (i) QPS thermal profile under a pulse length of 400s, (ii) burning time required for reaching the equilibrium temperatures, and (iii) time needed to cool the QPS. In the cases of lack of contact, the maximum temperature of the SB pebble beds exceeded the SB temperature limit, which may cause sintering of the pebbles and consequently inhibit the tritium release.
