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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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 Technology
Fusion Science and Technology
Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Fukada Satoshi, Nishikawa Masabumi, Sagara Akio
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1073-1077
Tritium | doi.org/10.13182/FST01-A11963386
Articles are hosted by Taylor and Francis Online.
Rates of continuous tritium recovery from a Flibe stream are calculated for a permeation window and a counter-current gas-bubble column. The area of the permeation window is estimated to be comparatively small unless very low tritium partial pressure is demanded for the system. It is probable that the tritium transfer rate is controlled not by permeation through the window material (Nb or ferrite steel) but diffusion in Flibe. Since tritium diffusion in the molten salt is also determination of the recovery rate in the gas-bubble column from Flibe to He, the evaluation of the tritium diffusion resistance in the molten salt is crucial for its design.
