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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
Mei-Ya Wang, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 335-340
Technical Paper | doi.org/10.13182/NSE14-97
Articles are hosted by Taylor and Francis Online.
For further improvements on thermal efficiency and operation safety, reactor internal pumps, instead of conventional recirculation systems, are adopted in an advanced boiling water reactor (ABWR). With the novel design of internal circulation, the traveling path and pattern of the recirculated liquid coolant in an ABWR is actually different from that of the coolant in a conventional boiling water reactor. To ensure operation safety, optimization of the coolant chemistry in the primary coolant circuit (PCC) of a nuclear reactor is essential no matter what type or generation the reactor belongs to. For a better understanding of the water chemistry in an ABWR, such as the one being constructed in the northern part of Taiwan, and for safer operation of this ABWR, in this study we conducted a proactive, thorough water chemistry analysis prior to the completion of this reactor. A well-developed computer code was used to investigate the effectiveness of hydrogen water chemistry (HWC) on the redox species concentrations and electrochemical corrosion potential (ECP) behavior of components in the PCC of the Lungmen ABWR in Taiwan. Our analyses indicated that the effective oxidant concentrations at the top of the downcomer location would be expected to be >100 ppb at 0.5 ppm [H2]FW at the original rated power. While an effective ECP reduction at 0.4 ppm [H2]FW was observed at the downcomer outlet, a 2.0 ppm [H2]FW was not enough to reduce the ECP below the Ecrit at the upper plenum outlet. In summary, the effectiveness of HWC in the PCC of an ABWR is expected to vary from location to location and eventually from plant to plant due to different degrees of radiolysis and physical dimensions in different ABWRs.