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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Michele Andreani
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 35-47
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3546
Articles are hosted by Taylor and Francis Online.
The pretest calculations of phase A of the International Standard Problem 42 (ISP-42) using the GOTHIC containment code are presented in this paper, together with the comparison with the experimental results.The focus of the analyses presented is on the mixing process in the drywells (DWs), initially filled with air, during the initial steam purging transient. Consequently, a large effort has been made to capture the flow pattern produced by the jet created by the steam injection, including in the model a large number of nodes for the three-dimensional (3-D) representation of the two vessels. The influence of the nodalization of the DWs on the calculation was investigated by means of two additional models using one volume for each of the DWs and a 3-D calculation using a much coarser mesh, respectively.Since the fluid in the DWs was well mixed and stratification occurred only below the injection level, all the models could predict very accurately the global variables such as pressure and temperature. The 3-D simulation also reproduced the wall and gas temperature distributions fairly well. The only (inferred) discrepancy with the test was the overprediction in the upward deflection of the buoyant steam jet.