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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Igor Peñalva, Gustavo A. Esteban, Natalia Alegría, Jon Azkurreta, María Urrestizala, Marta Malo, Belit Garcinuño, David Rapisarda
Fusion Science and Technology | Volume 80 | Number 3 | May 2024 | Pages 596-606
Research Article | doi.org/10.1080/15361055.2023.2194237
Articles are hosted by Taylor and Francis Online.
The determination of the transport parameters of the hydrogen isotopes in the eutectic lead-lithium (PbLi) alloy represents a key issue for the design of the different breeding blanket systems that are being developed based on this liquid metal. This is the case for the dual-coolant lithium-lead blanket where the values of the Sieverts’ constant and diffusivity will delimit the magnitude and the kinetics of the induced tritium flux produced by the breeding blanket toward the circuit of He for the refrigeration of the structures. In addition, the design (sizing and efficiency) of future tritium extraction systems of the breeding alloy or the He coolant purification system will be defined on the basis of these transport parameters.
Taking into account the current literature, there exists a very wide band (even more than three orders of magnitude) in the experimental results for the Sieverts’ constant obtained by different research groups using different experimental techniques. This dispersion band in terms of solubility is not acceptable from the point of view of the design of a breeding blanket for a fusion reactor. With the aim of reducing this dispersion of results, the Absorption-Desorption facility available at the University of the Basque Country (UPV/EHU) has been upgraded and new samples of high quality PbLi will be measured in the near future in collaboration with CIEMAT.
In this work, a complete theoretical model is described for the interaction between isotopes of hydrogen and the eutectic PbLi sample considering the particular boundary conditions for the absorption and desorption processes. This model has been specifically developed for the upgraded Absorption-Desorption facility available at the UPV/EHU, according to the new configuration of the experimental chamber made of glass and quartz and the geometry of the crucible made of tungsten that is designed to hold the PbLi sample. Three different phases are described (loading, pumping, and release) together with the boundary conditions that have been taken into account in each one. This way, different mathematical expressions for the concentration profile of the isotopes of hydrogen through the PbLi sample are posed for each phase so that the experimental measurements to be carried out in the upgraded Absorption-Desorption facility will be fitted to them, and as a result, the transport parameters will be obtained.