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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.
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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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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.
Dov Ingman, Leib Reznik
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 243-259
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33827
Articles are hosted by Taylor and Francis Online.
A multicomponent system, specified by a high level of power generation and transformation as a thermodynamics system with strong interaction between the elements, is considered in the reliability analysis. The reliability of each system element is dependent on the average energy of the system. The approach, which aims to give proper consideration to the system / element interaction, is based on the energy accumulation aspects of various processes of the element and the system deterioration. The phenomena of coherent blockages of core coolant channels for different geometrical configurations serve to demonstrate that there exists, in principle, a possibility of failure of the system through cooperative failures of its elements. The investigation is based on statistical thermodynamics, particularly on the approach of “phase transitions,” and also on the percolation theory results. The developed model has been employed to evaluate the propagation rate of the subchannel blockages under critical conditions. In spite of the simplified character of the model, it has demonstrated the necessity of including consideration of collective phenomena in the reliability analysis of multicomponent systems characterized by a high power level. The developed approach permits construction of a minimum set of generalized system parameters that describe the critical system behavior. A quantitative determination of these parameters and an application of the model to specific reactor core designs and severe transient scenarios will be the subject of further investigation.