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Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
N. Bekris, E. Hutter, J. Rodolausse
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1009-1013
Purification and Chemical Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22736
Articles are hosted by Taylor and Francis Online.
The Helium Cooled Pebble Bed (HCPB) Breeder Test Blanket concept of ITER will comprise 3 He circuits for the heat extraction, the coolant purification and the tritium removal generated by nuclear reactions in the lithium orthosilicate. Tritium production in the orthosilicate will inevitably also produce some tritiated water which should be removed from the helium purge gas stream before the extraction of tritium (mainly HT) by passing it through a liquid nitrogen cooled molecular sieve bed. To minimise the amount of adsorbed water in the molecular sieve beds a cryogenic cold trap (CT) will be included in the tritium extraction system (TES). The expected water concentration in this gas stream is of the order of 10 ppm by volume.A cold trap in a technical scale (1/6 of the ITER operating conditions) with design features meeting the requirements for water vapour trapping, i.e. variable cool-down rates and low velocity of the working gas, was used to investigate the water removal efficiency. In this paper we describe the first results obtained with small He throughputs as well as recent results obtained for medium and high He flow rates containing water vapour ranging from 10 to 16 ppmv.