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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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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.
Mark W. Crump, John C. Lee
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 192-210
Technical Paper | doi.org/10.13182/NSE81-A21353
Articles are hosted by Taylor and Francis Online.
We present a new computational method developed for fluid flows, in which both compressibility and thermal expansion effects are important. Application of the method in transient thermal-hydraulic analysis of nuclear steam generators is also presented. The fluid model is based on one-dimensional, nonlinear, single-fluid conservation equations for mass, momentum, and energy. An empirical slip flow model is included to enable description of two-phase flows as well as single-phase flows. Numerical solution is based on the implicit continuous-fluid Eulerian (ICE) method, which provides stable numerical solutions for compressible fluid flows. An extension of this method (designated as the EICE method) is developed to account for thermal expansion effects. This is achieved by including implicit energy dependence in coupled equations of mass, momentum, and state, and solving the full system of fluid equations through a two-step iterative technique. The development of the EICE method is presented and discussed, along with specific calculations for once-through and U-tube steam generator transients, natural flow oscillations, and a vessel blowdown transient.