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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.

Search results

Showing 1 to 5 of 5 (0.048 seconds)

Spelling suggestions: "subject:"buclear reactors codels"" "subject:"buclear reactors 2models""

1

Component modelling of a pressurized water reactor (PWR)

Elhabrush, Ahmed Mohamed January 1981 (has links)
No description available.
Pressurized water reactors.
Nuclear reactors -- Models.
2

A three region steam drum model for a nuclear power plant simulator (Brenda)

Slovik, Gregory Charles January 1980 (has links)
No description available.
Liquid metal fast breeder reactors.
Nuclear reactors -- Models.
3

Flooding limits in a simulated nuclear reactor hot leg

Krolewski, 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.
Mechanical Engineering.
Nuclear reactors Cooling
Nuclear reactor accidents
Nuclear reactors Models
4

Dynamic simulation of the Fast Flux Test Facility primary system

Sands, Mark Richard January 1981 (has links)
No description available.
Heat exchangers -- Mathematical models.
Nuclear reactors -- Models.
5

Top-down scaling analysis of the integral reactor vessel test facility

Graves, 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
Scaling
IRV
Nuclear reactors -- Models -- Evaluation

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