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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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.
Wolfgang Wulff
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 292-309
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3877
Articles are hosted by Taylor and Francis Online.
The paper presents integral methods for simulating two-phase flow transients in complex cooling systems, such as those in nuclear power plants. The methods are designed to simplify presently prevailing thermohydraulics simulation methods without a loss in simulation fidelity. The paper describes the inherent, but unnecessary, complexity of currently used simulation models, explains their inherent shortcomings, and foretells the impact of current code development trends on future capabilities to resolve safety issues in light of growing code complexities and inflexibility. The purpose of the paper is to present simpler alternatives.Integral methods described in the paper facilitate flexibility via computer-automated modularity and simplicity. They provide transparency through analytical methods. Integral methods replace partial by ordinary differential equations and thereby simplify the mathematical model formulation and achieve numerical integration with minimal numerical damping. The models connect important physical characteristic response times with the time step for numerical integration. The mixture model of nonhomogeneous, nonequilibrium two-phase flow, the integral of the volumetric flux divergence equation, and the integrals of the system of coupled loop momentum balances for interconnected loops in complex thermohydraulic systems play central modeling roles. A new and compact formulation of these equations facilitates a computerized system assembly of component models, each one being judiciously selected from a model library to impose the minimum necessary complexity. The method of assembly is based on linear algebra and accommodates any combination of phasic flow directions anywhere in the hydraulic system and at any time.