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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
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Kiriko Miyamoto, Yoshikazu Inoue, Tetsuo Iwakura, Hiroshi Takeda, Shoichi Fuma, Kei Yanagisawa, Nobuyoshi Isliii
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 483-487
Environment | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22636
Articles are hosted by Taylor and Francis Online.
A prototype of a tritium transfer model in the environment was developed for the purpose of dose estimation in our institute in 1995. The model consists of many compartments representing tritium reservoirs in a hydrological cycle in the local hydrosphere, and reservoirs in food chains in the aquatic and terrestrial environments. Underground tritium reservoirs are defined as three aquifers in the model, although the number of aquifers might depend on the site. Our present work was focused on an application of the model to an area with nuclear facilities, Tokai-mura, Japan, where there is only one aquifer. The Shinkawa (Shin River) flows through the Muramatsu area between two nuclear facilities, and then into the Pacific Ocean. About 2000 people live in the area and some use groundwater as a convenient daily water source as well as village tap water. Samples at 16 rainwater and 20 groundwater sites from the Muramatsu area (5 km2) as well as 3 groundwater sites from an inland area were taken during 1983–90, and tritium concentrations were measured. In order to investigate the scale of the drainage system of the Shinkawa basin, time series data of excess tritium in rainwater and groundwater were applied to our transfer model. As a result, the volume of the aquifer was calculated as half of the annual rainfall in the area. This is so small that the tritium concentration of the groundwater has a quick time trend response to input of tritium from rainwater. The results can be used to estimate population dose of the residents in the Muramatsu area.