ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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June 2025
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May 2025
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.
Joseph A. Naser
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 373-379
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32782
Articles are hosted by Taylor and Francis Online.
The RETRAN system thermal-hydraulics analysis code has been used to simulate the three turbine trip tests at the Peach Bottom Unit 2 boiling water reactor. The latest analysis used the dynamic slip, profile fit subcooled void, and point kinetics models in RETRAN-02. The results demonstrated that RETRAN is capable of simulating operational transients such as turbine trips. The analysis aided in understanding physical phenomena not well known such as the transient behavior of the steam bypass system and the pressure vessel. Experience gained in this work pointed out the importance of having good experimental data for code qualification purposes. This includes knowing the initial conditions, boundary conditions, control system and equipment parameters, and operator actions. The analysis of these three tests will be repeated in the future using one-dimensional kinetics, improved steam separator, and mechanistic subcooled voiding models.