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Component modelling of a pressurized water reactor (PWR)Elhabrush, Ahmed Mohamed January 1981 (has links)
No description available.
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A three region steam drum model for a nuclear power plant simulator (Brenda)Slovik, Gregory Charles January 1980 (has links)
No description available.
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Flooding limits in a simulated nuclear reactor hot legKrolewski, Susan M January 1980 (has links)
Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND ENGINEERING. / Bibliography: leaf 31. / by Susan M. Krolewski. / B.S.
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Dynamic simulation of the Fast Flux Test Facility primary systemSands, Mark Richard January 1981 (has links)
No description available.
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Top-down scaling analysis of the integral reactor vessel test facilityGraves, Joshua D. 07 December 2012 (has links)
Oregon State University has conducted research in collaboration with TerraPower, LLC,
to perform a top-down scaling analysis of an integrated test facility. The goal of this
facility is to simulate transient and quasi-steady phenomena at a reduced scale,
including steady-state operation, pump coastdown, natural circulation, reactor head heat
transfer, and coolant stratification. To support this goal, this thesis presents the
methodology and analysis by which approximate facility dimensions were generated.
This analysis includes implementation of the hierarchical two-tiered scaling
methodology, as outlined by the Nuclear Regulatory Commission and optimization
through the general reduced gradient methodology. / Graduation date: 2013
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