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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
M.A. Hoffman, Y.T. Lee
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1557-1568
Inertial Fusion Reactor Studies | doi.org/10.13182/FST92-A29942
Articles are hosted by Taylor and Francis Online.
The HYLIFE-II concept uses the molten salt, Flibe as the primary coolant for the liquid jet flows in the reactor and uses sodium fluoroborate (NaBF4) in the secondary loop. The impact of these molten salts on the direct capital cost of the balance of plant (BOP) and on the cost of electricity (COE) has been investigated. The RUBY computer code has been written specifically for these molten salts and includes detailed analytical models for the intermediate heat exchangers (IHX's) and the steam generator system consisting of separate evaporators and superheaters. Using the RUBY code, the design of these large and costly heat exchangers and the associated tritium removal system has been optimized to yield the minimum COE. The cost models used in the code are described and the results of the optimization are given.
