Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
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Showing 1 to 7 of 7 for “"RELAP"”.
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Modeling Two-Phase Flow in the Downcomer of a Once-Through Steam Generator using RELAP5/MOD2
… (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 first-of-a-kind (FOAK) study conducted at Oconee Unit I in Oconee, …
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Dynamic simulation of nuclear hydrogen production systems
… been conducted by using legacy codes, such as RELAP and MELCOR, and their focus has been the operation of nuclear power plants. However, traditional legacy codes are not appropriate to simulate nuclear hydrogen production. The simulation of a nuclear reactor itself is already complex because it …
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Safety of light water reactor fuel with silicon carbide cladding
… code FRAPCON-3.4 (modified here for SiC) and RELAP-5 (to determine coolant conditions). It is concluded that a PWR fuel rod with SiC cladding can extend the fuel residence time in the core, while keeping the internal pressure level within the safety assurance limit during steady-state and loss …
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The design of a compact integral medium size PWR : the CIRIS
… to flow changing flow conditions. A complete RELAP5 model of the IRIS reactor, along with PCHE and IXAF design representation, was developed. The PCHE RELAP model was first benchmarked against the stand-alone code and their agreement was demonstrated successfully. The short and long term …
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Development, Evaluation and Improvement of Correlations for Interphase Friction in Gas-Liquid Vertical Upflow
… calculations published in the manuals of RELAP5/MOD2, RELAP5/MOD3.3, RELAP5-3D and TRACE. The findings have generally shown that the equations in the manuals provide very inaccurate approximations of the interphase friction compared to the interphase friction that was found via force …
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Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors
This work introduces a new method to increase the safety of Boiling Water Reactors (BWRs) during the BWR instability and Loss of Coolant Accidents (LOCA). The method is based on a device called Reverse Flow Restriction Device (RFRD) and its purpose is to allow the flow in the forward direction, but …
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Development of a coupled CFD—system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors
… a series of assembly level CFD simulations. RELAP5-3D is introduced in Part 3 as the nuclear system code for coupled CFD—System-code development. UDF feature of FLUENT is used to develop the interface for this coupling effort. This innovative coupling approach is verified by comparing the …