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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.
Ryuji Koga
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 239-249
Technical Paper | doi.org/10.13182/NSE76-A27357
Articles are hosted by Taylor and Francis Online.
A burnup control problem during a reactor core life is considered and solved by making use of a neutron-governing equation that is particularly devised to fit power reactors. Space-dependent parameters are expanded using Walsh functions, and the burnup process is described in terms of the expansion coefficients. By applying the Walsh-function expansion to a newly devised neutron-governing equation, CUMULUS, the criticality condition is established through a more simplified approach, and the system structure of a two-region reactor can be illustrated graphically. Using the above burnup model, an optimal control problem to maximize the average burnup at the end of a core life is considered, and numerical test problems are solved.