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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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Fusion Science and Technology
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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.
P.A. Finn, R.G. Clemmer, L. Greenwood, A. Lide, D.K. Sze, J.L. Anderson, R. Sherman, J.R. Bartlit, Y. Naruse, H. Yoshida
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 680-686
Blanket and Shield Design | doi.org/10.13182/FST89-A39776
Articles are hosted by Taylor and Francis Online.
A breeder blanket interface for an aqueous lithium salt blanket is defined for TSTA. High calculated radiolysis rates result in a high overpressure in the blanket and the need for a depressurizer and a recombiner system. High projected corrosion rates for stainless steel and for beryllium result in high activity levels in the blanket and the possible dissolution of the beryllium balls. The required tritium processing systems are complex, involving seven separation steps. A flow sheet is presented of the needed tritium systems. The main processing units to recover tritium from the salt solution are a flash evaporator with condenser, a water distillation unit, and a vapor phase chemical exchange (VPCE) unit. The gas product stream from the blanket has an H/T ratio of 105 which requires a dedicated cryodistillation unit of very high capacity. This unit has a first column with a diameter of almost one meter to decrease the H/T ratio to 10.
