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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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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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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.
Ronald W. King, Erwin C. Filewicz
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 32-42
Technical Paper | Reactor | doi.org/10.13182/NT81-A32687
Articles are hosted by Taylor and Francis Online.
The Experimental Breeder Reactor II (EBR-II) is an unmoderated, sodium-cooled reactor with a design power level of 62.5 MW(thermal). The design uses a submerged pool concept in which the reactor and fuel handling components are contained in a primary tank filled with sodium. The in-tank fuel handling is done remotely with no visual contact of the fuel subassemblies or the in-tank portion of the fuel handling equipment. The fuel handling operations, therefore, depend on precise, predictable positioning of all equipment and subassemblies. In July 1978, during normal fuel handling operations, it was discovered that one of the subassemblies in the in-tank storage basket for reactor subassemblies was not in the proper position to be handled with the subassembly transfer arm. Months of diagnostic evaluation of the actual position and shape of the subassembly resulted in a full-size mockup of the equipment and of the subassembly involved. The diagnostic measurements were duplicated with the mockup, a special system for retrieving the subassembly was designed and built, and a procedure was prepared. Using the mockup, the special equipment and procedure were thoroughly tested, modified, and retested. The subassembly was retrieved from the storage basket and primary tank on May 11, 1979, with no major difficulties. During the time between the discovery of the problem and the retrieval of the sub-assembly, EBR-II reactor operations continued as normal except for minor inconveniences during fuel handling operations because of the position of the damaged subassembly. The overall success of this project gave confidence that abnormal situations of this type in a sodium-cooled, pot-type reactor can be handled, without visual contact, through careful planning and preparation.