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Thermal Hydraulics
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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
C. E. Kessel, F. M. Poli
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 220-239
Technical Paper | doi.org/10.13182/FST14-793
Articles are hosted by Taylor and Francis Online.
The conservative physics and conservative technology tokamak power plant ARIES-ACT2 has a major radius of 9.75 m at an aspect ratio of 4.0 and has strong shaping with elongation of 2.2 and triangularity of 0.63. The plasma current is 14 MA, and the toroidal field at the plasma major radius is 8.75 T, making the maximum field at the toroidal field coil 16 T. The no-wall βN reaches ∼2.4, limited by n = 1 external kink mode, and can be extended to 3.2 with a stabilizing shell behind the ring structure shield. The bootstrap current fraction is 77% with a q95 of 8.0, requiring ∼4.0 MA of external current drive. This current is supplied with 30 MW of ion cyclotron radio frequency/fast wave and 80 MW of negative ion neutral beams. Up to 1.0 MA can be driven with lower hybrid (LH) with no wall, and 1.5 or more MA can be driven with a stabilizing shell. Electron cyclotron was examined and is most effective for safety factor control over ρ ∼0.2 to 0.6 with 20 MW. The pedestal density is ∼0.65 × 1020/m3, and the temperature is ∼9.0 keV. The H98 factor is 1.25, n/nGr = 1.3, and the net power to LH threshold power is 1.3 to 1.4 in the flattop. Because of the high toroidal field and high central temperature, the cyclotron radiation loss was found to be high depending on the first-wall reflectivity.