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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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From the Pages of Nuclear News: Industry update July 2025
Here is a recap of industry happenings from the recent past:
Utah moves to forefront of advanced nuclear development
EnergySolutions has signed a memorandum of understanding to partner with Utah’s Intermountain Power Agency and the Utah state government to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta. The MOU calls for the leveraging of existing infrastructure at the IPP site; potential development of small modular reactor nuclear baseload power; potential synergy with the existing Intermountain Power Agency energy hub and advanced grid stabilization technologies; collaboration with local, state, and regional stakeholders; and commitment to rural economic development and job creation in the state. The partnership is aligned with Utah Gov. Spencer Cox’s Operation Gigawatt, an initiative to double Utah’s energy production over the next 10 years.
Alice Ying, Haibo Liu, Mohamed Abdou
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 303-308
Divertor and High-Heat-Flux Components | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST64-303
Articles are hosted by Taylor and Francis Online.
Available data and mathematical formulations concerning tritium transport in the FW/Divertor with tungsten and beryllium as plasma facing materials were implemented in the commercial code COMSOL Multiphysics. The goal is to develop a CAD-based multiphysics modeling capability so that FW/Divertor temperature and geometric features can be readily taken into consideration while tritium permeation to the primary coolant in a prototypical PFC can be more realistically addressed. This development began with the simulation of ion implantation experiments, validated against existing laboratory experimental results. Analysis shows that with ITER FW where Be is used as the plasma facing material, the low operating temperature, erosion, and the dwell time greatly hinder tritium bulk diffusion, permeation, and inventory accumulation. However, under DEMO high-temperature operating conditions, tritium can quickly diffuse through tungsten to structural material and reach a steady state inventory after a relatively short time. Additionally, its permeation to the coolant can be reduced when the Soret effect is considered. The findings and challenges of developing a 3-D predictive capability for tritium transport in a FW/Divertor PFC are discussed.