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.
Abdelhamid Dokhane, Stefano Canepa, Hakim Ferroukhi
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 341-353
Technical Paper | Fission Reactors / Radiation Transport and Protection | doi.org/10.13182/NT13-A19423
Articles are hosted by Taylor and Francis Online.
For stability analyses of the Swiss operating boiling water reactors, the methodology employed and validated so far at the Paul Scherrer Institute (PSI) was based on the RAMONA-3 code with a hybrid upstream static lattice/core analysis approach using CASMO-4 and PRESTO-2. More recently, steps were undertaken toward a new methodology based on the SIMULATE-3K (S3K) code for the dynamical analyses combined with the CMSYS system, which relies on the CASMO/SIMULATE-3 suite of codes and was established at PSI to serve as framework for the development and validation of reference core models of all the Swiss reactors and operated cycles.This paper presents a first validation of the new methodology on the basis of a benchmark recently organized by a Swiss utility and including the participation of several international organizations with various codes/methods. Now in parallel, a transition from CASMO-4E (C4E) to CASMO-5M (C5M) as basis for the CMSYS core models was also recently initiated at PSI. Consequently, it was considered adequate to address the impact of this transition both for the steady-state core analyses as well as for the stability calculations and to achieve thereby an integral approach for the validation of the new S3K methodology. Therefore, a comparative assessment of C4 versus C5M is also presented in this paper, with particular emphasis on the void coefficients and their impact on the downstream stability analysis results.