ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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 61 | Number 2 | May 1983 | Pages 313-328
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33199
Articles are hosted by Taylor and Francis Online.
The RETRAN-01 system thermal-hydraulics analysis code has been used to simulate the Peach Bottom Unit 2 boiling water reactor (BWR) turbine trip tests. Since these studies have been performed, a second version of the code, RETRAN-02, has been developed and released. The RETRAN-02 code has a number of physical models that did not exist in RETRAN-01. These include slip between phases, subcooled voiding, special steam separator, one-dimensional kinetics, and iterative numerics models. The new models that exist in RETRAN-02 allow a more realistic modeling of the physical phenomena that occur, in particular, in a BWR. The effect of these new models is studied through the analysis of one of the Peach Bottom turbine trip tests. Each model’s effect is easily observed since the models are applied one at a time. It was demonstrated that if the same options are used in both RETRAN-01 and RETRAN-02, essentially the same results are obtained. This is important because of the large amount of validation that has been performed with RETRAN-01. The results using the new models demonstrate that they are capable of more realistically describing the physical phenomena that occur during a turbine trip in a BWR.