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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
Richard Simms, Robert K. LO, William F. Murphy, Alan B. Rothman, George S. Stanford
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 225-241
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32526
Articles are hosted by Taylor and Francis Online.
In a transient overpower (TOP) accident, the fuel element failure threshold is a function of the rate of reactivity increase and the fuel microstructure. Test E8 simulated a hypothetical $3/s TOP accident in a liquid-metal fast breeder reactor using seven (Pu,U)O2 fuel elements of the fast test reactor (FTR) type. The test elements were pre-irradiated at 30 kW/m in the Experimental Breeder Reactor II to 5 at.% burnup, leading to a low-to-moderate power micro structure typical of FTR fuel Data from test vehicle sensors, hodoscope, and post-test examinations were used to deduce the sequence of events occurring within the test zone. The initial fuel failure event occurred abruptly at ∼29 times the nominal power level at an estimated average enthalpy of ∼925 kJ/kg relative to 20°C, with 50% of the fuel cross-sectional area above the solidus at the suspected failure site. After the initial failure, ∼2% of the fuel was ejected above the top of the active fuel region. Sodium voiding occurred rapidly. An upper blockage was formed that apparently prevented further fuel dispersal. Inherent test vehicle limitations, loss of flow tube geometry, and nontypical power generation after fuel element failure may have caused a departure from the fuel motion predicted for the FTR conditions. No violent fuel-coolant interactions were observed in the test.