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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Jack L. McElroy, Albert G. Blasewitz, Kenneth J. Schneider
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 69-82
Technical Paper | Radioactive Waste | doi.org/10.13182/NT71-A15900
Articles are hosted by Taylor and Francis Online.
Demonstration of the solidification of high-level radioactive waste by the pot, spray, and phosphate glass solidification processes has been successfully completed by Battelle-Northwest. More than 50 million curies of radionuclides were processed and collected in 6-, 8-, and 12-in. diam containers during 33 engineering-scale demonstration runs in the Waste Solidification Engineering Prototypes (WSEP). The maximum self-generating heat rate values in the solidified wastes for an 8-in.-diam pot ranged from 205 W/liter for the spray solid to 85 W/ liter for the pot calcine. Wastes equivalent to those from thermal power reactors with exposures as high as 45 000 MWd/MT at 30 MW/MT were demonstrated. The WSEP auxiliary equipment consisting of an evaporator, an acid fractionator, filters, and a caustic scrubber reduced radionuclides in the stack gas to well below government release limits. The final liquid effluent from WSEP contains radioruthenium that is 104 to 106 times allowable government release values. Strontium and other nonvolatile materials are present to a much smaller extent. Initial studies indicated that the effluent water and acid streams from the waste solidification processes are sufficiently low in volume and radioactivity that they can be reasonably recycled into the fuel reprocessing plant operation. The pots of solidified wastes from the WSEP runs are undergoing testing to determine the effects of storage temperature (air or water), radiation, and feed type on the physical and chemical properties of the solidified wastes.