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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
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Latest News
Bipartisan nuclear waste bill introduced in U.S. House
U.S. representatives Mike Levin (D., Calif.) and August Pfluger (R., Texas) have introduced the bipartisan Nuclear Waste Administration Act of 2024, which would establish an independent agency to manage the country’s nuclear waste.
In addition to establishing a new, single-purpose administration to manage the back end of the nuclear fuel cycle, the bill would direct a consent-based siting process for nuclear waste facilities and ensure reliable funding for managing nuclear waste by providing access to the Nuclear Waste Fund. According to Pfluger and Levin, the bill’s provisions are in line with recommendations from the Blue Ribbon Commission on America’s Nuclear Future.
G. Bellanger, J. J. Rameau
Fusion Science and Technology | Volume 32 | Number 2 | September 1997 | Pages 196-219
Technical Paper | Tritium System | doi.org/10.13182/FST97-A19891
Articles are hosted by Taylor and Francis Online.
To better understand the differences between R30003 alloy corrosion in tritiated water and in H2O, a detailed study was made of the oxide layers produced in the former medium. The R30003 alloy was selected because of its nuclear corrosion resistance and its hardness, ensuring leaktightness when assembled with soft alloys. The characteristics and morphology of the formed oxide were investigated in corrosion potential, passive, and passive-transpassive regions where breakdown occurs. With tritiated water, the repassive potential is slightly lower than that obtained with H2O. Consequently, localized corrosion, which leads to corrosion in oxide sublayers, is greater and is produced by the effects of excited radiolytic products formed by time-dependent O3H− diffusion into the oxide. If enough tritium decay energy is absorbed by the oxide layer, excited and ionized states of the oxide are formed. Thus, reactive radiolytic species and voids accumulate in a small volume below the oxide surface. Spreading of these voids causes oxide cracking, leading to peeling and wall formation. Mechanisms for both processes and the electrochemical properties are described. The majority of the ionic carriers are in the peels, contributing to oxide delamination and thus steel degradation.