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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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Fusion Science and Technology
House Dems introduce clean energy bill for net zero
Democratic leaders in the House last week introduced the Climate Leadership and Environmental Action for our Nation’s Future Act (the CLEAN Future Act, or H.R. 1512), a nearly 1,000-page piece of climate change–focused legislation establishing, among other things, a federal clean electricity standard that targets a 50 percent reduction in greenhouse gas emissions from 2005 levels by 2030 and net-zero emissions by 2050.
The bill, a draft version of which was released in January 2020, presents a sweeping set of policy proposals, both sector-specific and economy-wide, to meet those targets. The final version includes a number of significant revisions to bring the legislation into closer alignment with President Biden’s climate policy campaign pledges. For example, the bill’s clean electricity standard would require all retail electricity suppliers to provide 80 percent clean energy to consumers by 2030 and 100 percent by 2035. (A six-page fact sheet detailing the updates is available online.)
J. N. Brooks et al.
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 669-677
Technical Paper | Fusion Energy - Divertor and Plasma-Facing Components | dx.doi.org/10.13182/FST05-A763
Articles are hosted by Taylor and Francis Online.
The US Advanced Limiter-divertor Plasma-facing Systems (ALPS) program is developing the science of liquid metal surface divertors for near and long term tokamaks. These systems may help solve the demanding heat removal, particle removal, and erosion issues of fusion plasma/surface interactions. ALPS combines tokamak experiments, lab experiments, and modeling. We are designing both static and flowing liquid lithium divertors for the National Spherical Torus Experiment (NSTX) at Princeton. We are also studying tin, gallium, and tin-lithium systems. Results to date are extensive and generally encouraging, e.g., showing: 1) good tokamak performance with a liquid Li limiter, 2) high D pumping in Li and non-zero He/Li pumping, 3) well-characterized temperature-dependent liquid metal surface composition and sputter yield data, 4) predicted stable low-recycle improved-plasma NSTX-Li performance, 5) high temperature capability Sn or Ga potential with reduced ELM & disruption response concerns. In the MHD area, analysis predicts good NSTX static Li performance, with dynamic systems being evaluated.