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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.
Trine-Yie Dawn
Nuclear Science and Engineering | Volume 77 | Number 3 | March 1981 | Pages 344-351
Technical Note | doi.org/10.13182/NSE81-A19842
Articles are hosted by Taylor and Francis Online.
The method of D-partitions is introduced to study the stability property of the reactor dynamic equation with six-delay-group representation. Two kinds of feedback models are considered—the delayed and the two-path temperature feedback. The stability region in parameter space, the effect of delayed neutrons, and the unconditional stability of the two-path temperature feedback are discussed in detail. The corresponding results of the one-delay-group model, one-group prompt-jump approximation, and effective lifetime model are also presented for comparing and discussing the validity or accuracy of these simplified kinetic models.
