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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.
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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
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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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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.
Farid Bamdad
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 578-582
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32801
Articles are hosted by Taylor and Francis Online.
Analyses of depressurization rates other than full Automatic Depressurization System (ADS) blowdown are performed to study the effect on the core cooling capability and to minimize thermal stress on the reactor vessel. Four different arbitrary conditions are demonstrated in order to verify the possibility of defining a range over which the slow depressurization can be performed without uncovering the core. The first two cases demonstrate the sensitivity to the depressurization starting time by manual blowdown at 25% capacity at 5 and 8 min into the transient. Two other cases are chosen to show the possible effects of the rate of depressurization. This is done by blowing down at 50 and 75% steam relief capacity at 5 min after the initiation of the transient. For all these cases it is assumed that an additional 25% flow discharge exists due to a stuck open relief valve. The last case demonstrated that early full ADS blowdown might flash water mixed with steam through the relief valves. This is due to the sudden expansion in the reactor vessel inventory upon pressure relief and high water level at the time of depressurization. This, however, is of paramount importance in the integrity and design operating conditions of the ADS valves and steam piping system.