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NRC looks to leverage previous approvals for large LWRs
During this time of resurging interest in nuclear power, many conversations have centered on one fundamental problem: Electricity is needed now, but nuclear projects (in recent decades) have taken many years to get permitted and built.
In the past few years, a bevy of new strategies have been pursued to fix this problem. Workforce programs that seek to laterally transition skilled people from other industries, plans to reuse the transmission infrastructure at shuttered coal sites, efforts to restart plants like Palisades or Duane Arnold, new reactor designs that build on the legacy of research done in the early days of atomic power—all of these plans share a common throughline: leveraging work already done instead of starting over from square one to get new plants designed and built.
Yasushi Yamamoto, Mai Ichinose, Fumito Okino, Kazuyuki Noborio, Satoshi Konishi
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 558-562
Blanket Design and Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12442
Articles are hosted by Taylor and Francis Online.
In the design of the fusion blanket, it is important to gather generated tritium as quick as possible and supply them to a fuel supply system for keeping fuel cycle and reducing tritium inventories in the fusion reactor at the same time.In the advanced blanket concept which uses Lithium-Lead (LiPb) as the working fluid for heat removal, neutron shielding and tritium breeding, collection of generated tritium is thought not to be difficult as the solubility of hydrogen into the LiPb is small enough. But examination and design of these collecting systems was not fully studied.In this paper, we made the conceptual design of the tritium collecting device using vacuum sieve tray, and studied formation process of LiPb droplets by making a simple experimental device. It was found that droplets of about 0.9-mm radius were formed at 8~12-cm distance from nozzle when LiPb discharges from the nozzle with 1-mm diameter hole at pressure of 2.5×104 Pa. Using this value, it is estimated that the tritium collecting efficiency of 45% can be achieved with 1-m height single stage sieve tray at temperature of 500 °C.