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Showing 1 to 20 of 56 for “"Steam Generator"”.
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Boiling heat transfer characteristics of steam generator U-tube fouling
The boiling heat transfer characteristics of steam generator u-tube fouling deposits were identified by developing a boiling heat transfer model and determining its accuracy through the comparison of calculated and experimental results. Magnetite deposits were fabricated in the laboratory and were …
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Mechanisms for automated toolhead changing in nuclear steam generator robotics
… in human radiation exposure and reduced steam generator service time.
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Microstructural Characterization of Thermally Treated Alloy 690 Steam Generator Tubing Material
Made available in DSpace on 2017-07-06T18:55:36Z (GMT). No. of bitstreams: 2 Nevling_James_E_MS.pdf: 34911212 bytes, checksum: 81d5267ee9815385edea94f1d94351e4 (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1988
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Feedback Control of a Large Steam Generator Using Vector Performance Index
Made available in DSpace on 2014-12-10T19:07:27Z (GMT). No. of bitstreams: 1 7514129.pdf: 6351621 bytes, checksum: 7198471aa3f89e07529e0931dcfeb89a (MD5) Previous issue date: 1975
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Assessment of a compact steam generator aided by computational fluid dynamics
Steam generators are an essential component in nuclear power plants which serve to transfer thermal power from a liquid coolant to steam by boiling water. Even with many advancements in the designs of steam generators, they still require extremely large sizes and have high costs which are major …
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Corrosion fatigue in nickel base alloys for nuclear steam generator applications
Thesis (Sc.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.
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An investigation of flow-induced vibrations of a steam-generator tube
A typical failure in a heat exchanger is the breakdown of a tube due to impact-sliding wear. We investigate the dynamic behavior of a tube subjected to cross flow and study the stability of periodic solutions, bifurcations, and the route to chaos. The fluid-stiffness-controlled mechanism is chosen …
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A performance model for a helically coiled once-through steam generator tube
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979.
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Computational fluid dynamic (CFD) optimization of microfluidic mixing in a MEMS steam generator
… for aqueous chemical reactants in a micro steam generator. The study focuses on the geometric optimization of a static micromixer channel by considering the trade-off between mixing quality and pressure drop. Both zigzag and straight channels are evaluated, in addition to channels with …
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Bayesian Belief Network (BBN)-based advisory system development for steam generator replacement project management
… Network (BBN) approach was selected to model the steam generator replacement proj ect management problem, where the situation holds inherently large uncertainty and complexities, since it has a superior ability to treat complexities, uncertainty management, systematic decision making, inference …
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CFD Analysis of Aspirator Region in a B&W Enhanced Once-Through Steam Generator
… the aspirator region of an enhanced once-through steam generator of the Babcock & Wilcox design. This information is important to the development of accurate RELAP5 models, steam generator level calculations, steam generator downcomer models, and flow induced vibration analyses. The OpenFOAM CFD …
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Computational Fluid Flow Analysis of the Enhanced-Once through Steam generator Auxiliary feedwater system
The once through steam generator (OTSG) is a single pass counter flow heat exchanger in which primary pressurized water from the core is circulated. Main Feedwater is injected in an annular gap on the outer periphery of the steam generator shroud such that it aspirates steam to preheat the …
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Nonlinear digital computer control for the steam generator system in a pressurized water reactor plant
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1987.
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Inspection of Ferromagnetic Support Structures From Within Alloy 800 Steam Generator Tubes Using Pulsed Eddy Current
… aspect of component lifetime management. Nuclear steam generator (SG) tubes are the thinnest barrier between irradiated primary heat transport system and the secondary heat transport system, whose components are not rated for large radiation fields. Conventional eddy current testing (ECT) and …
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Modeling Two-Phase Flow in the Downcomer of a Once-Through Steam Generator using RELAP5/MOD2
… model of the downcomer of the once-through steam generator (OTSG) developed by Babcock & Wilcox, using RELAP5/MOD2. While the physical model can be easily developed, several parameters are left to be adjusted to optimally model the downcomer and match data that was retrieved in a …
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The effect of steam generator tube plugging on its overall thermal performance - A Systems CFD-Based Study
The steam generator in a pressurized water reactor power plant acts as a fission product barrier between primary and secondary system. Material failure of the tube bundle barrier could therefore lead to a release of radioactive product into the secondary side. Several repair methods have been used …
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Multiphysics modeling of activity transport and evolution of CRUD and steam generator oxides in pressurized water reactors
… products on ex-core structures, such as steam generators and piping, can cause increased radiation fields and higher dose exposures for plant workers. To better understand the mechanisms of corrosion product activity transport and evolution in the primary coolant loop, a crud source term …
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Hardware-in-the-loop simulation of pressurized water reactor steam-generator water-level control, designed for use within physically distributed testing environments
… to represent digital sensing and control of steam generator water-level. The model was created with an intention to serve as a component within a larger, distributed digital systems conceptual testing facility. In the present application, a software model simulates a nuclear pressurized water …
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Degradation Mechanisms of Copper and Copper Alloys
… attack of Monel 400, a Ni-Cu alloy used as a steam generator tubing material, is proposed. Dealloying of Monel is contingent on the accumulation of Cu2+, which stabilizes metallic copper. This is achieved in the nuclear steam generator by accumulation of corrosion products within hideout …
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Formation and Quantification of Corrosion Deposits in the Power Industry
… side of pressurized water reactor (PWR) steam generator systems is one of the main contributors to the high maintenance costs of these generators. Formation and transport of corrosion products formed due to the presence of impurities, metals and metallic oxides in the secondary side of …
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