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
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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.
M. R. Mataušek
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 440-457
Technical Paper | doi.org/10.13182/NSE74-A23375
Articles are hosted by Taylor and Francis Online.
The loop considered consists of an equivalent downcomer and a channel divided into a heated test section and an unheated riser. The preliminary structure of the lumped-parameter model is obtained by integrating partially, over the space coordinate, the system of nonlinear partial differential equations that state the mass, energy, and momentum conservation. The same formalism, however, should not be used for specifying the final structure of the model; it is shown that in this way it is not possible to represent adequately the basic mechanism of hydrodynamic instability, i.e., to define the interaction between the mass velocity and the void fraction, resulting from the friction in the boiling part of the heated test section. A procedure is proposed for specifying the final structure of the lumped-parameter model that can be adequately used instead of distributed parameter models in a wide range of system parameters and operating conditions. The model SINOD is formulated in terms of four nonlinear first-order ordinary differential equations and one time lag. Since the time lag can be neglected in most analyses, the model reduces to a system of only three nonlinear first-order ordinary differential equations. An important particularity of the model is that both the steady-state and the dynamic calculations can be performed by solving the same system of differential equations. The input data are the parameters specifying the geometry of the test loop, the physical parameters of the fluid, the channel inlet, and the riser outlet pressure drop coefficients. The two-phase friction multiplier and the slip ratio correlations are arbitrary. The validity of the proposed model is examined by comparing the results with the experimental data obtained on the test loops FRÖJA, FRIGG, SKÄLAVAN, and the Halden Loop, as well as with the results obtained using the distributed parameter models HYDRO and RAMONA.