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Attainable region (AR) theory is a branch of chemical engineering, specifically chemical reaction engineering, that uses geometric and mathematical optimization concepts to assist in the design of networks of chemical reactors. AR theory is a method to help define the best reactor flowsheet using graphical techniques for a desired duty or ...
This information can be used to obtain information on liquid equilibria, which is useful in many thermodynamic calculations, such as chemical reactor design, and distillation calculations. The UNIFAC model was first published in 1975 by Fredenslund, Jones and John Prausnitz , a group of chemical engineering researchers from the University of ...
A real plug flow reactor has a residence time distribution that is a narrow pulse around the mean residence time distribution. A typical plug flow reactor could be a tube packed with some solid material (frequently a catalyst). Typically these types of reactors are called packed bed reactors or PBR's.
This smaller 600 megawatt electrical reactor was notable for its incorporation—for the first time ever in a light water reactor [citation needed] —of "passive safety" design principles. The concept of passive safety means that the reactor, rather than requiring the intervention of active systems, such as emergency injection pumps, to keep ...
Future work focuses on optimizing the basic design and performing coupled 3D calculations, like thermohydraulics, fuel performance, and neutronics to determine detailed behavior and operation. [ 13 ] As of 2010, there has also been a growing interest in mobile floating nuclear power plants, considered to be nuclear microreactors.
RELAP5-3D is an outgrowth of the one-dimensional RELAP5/MOD3 code developed at Idaho National Laboratory (INL) for the U.S. Nuclear Regulatory Commission (NRC). The U.S. Department of Energy (DOE) began sponsoring additional RELAP5 development in the early 1980s to meet its own reactor safety assessment needs.
DRAGON 3.05D, Reactor Cell Calculation System with Burnup nesc0784 DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant nea-1683 ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses nea-1916 FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets
It is often used to design large-scale measurements providing a significant time and cost savings to the community. LANL's latest version of the MCNP code, version 6.2, represents one piece of a set of synergistic capabilities each developed at LANL; it includes evaluated nuclear data (ENDF) and the data processing code, NJOY.