Author: Carl C. St. PierrePublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 150
Book Description
Frequency-response Analysis of Steam Voids to Sinusoidal Power Modulation in a Thin-walled Boiling Water Coolant Channel
Author: Carl C. St. PierrePublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 150
Book Description
Proceedings of the International Symposium on Two-Phase Systems
Author: G. HetsroniPublisher: Elsevier
ISBN: 1483160505
Category : Science
Languages : en
Pages : 779
Book Description
Proceedings of the International Symposium on Two-Phase Systems
ANS Proceedings
Author: Power Reactor Technology
Author: Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1084
Book Description
Multiphase Flow Dynamics 5
Author: Nikolay Ivanov KolevPublisher: Springer Science & Business Media
ISBN: 3642206018
Category : Technology & Engineering
Languages : en
Pages : 839
Book Description
The present Volume 5 of the successful book package "Multiphase Flow Dynamics" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step demonstrate the success of the different ideas and models. After an introduction of the design of the reactor pressure vessels for pressurized and boiling water reactors the accuracy of the modern methods is demonstrated using large number of experimental data sets for steady and transient flows in heated bundles. Starting with single pipe boiling going through boiling in the rod bundles the analysis of complete vessel including the reactor is finally demonstrated. Then a powerful method for nonlinear stability analysis of flow boiling and condensation is introduced. Models are presented and their accuracies are investigated for describing critical multiphase flow at different level of complexity. Basics of designing of steam generators, moisture separators and emergency condensers are presented. Methods for analyzing a complex pipe network flows with components like pumps, valves etc. are also presented. Methods for analysis of important aspects of the severe accidents like melt-water interactions, external cooling and cooling of layers of molten nuclear reactor material are presented. Valuable sets of thermo-physical and transport properties for severe accident analysis are presented for the following materials: uranium dioxide, zirconium dioxide, stainless steel, zirconium, aluminum, aluminum oxide, silicon dioxide, iron oxide, molybdenum, boron oxide, reactor corium, sodium, lead, bismuth, and lead-bismuth eutectic alloy. The emphasis is on the complete and consistent thermo dynamical sets of analytical approximations appropriate for computational analysis. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics. This present second edition includes various updates, extensions, improvements and corrections. This present second edition includes various updates, extensions, improvements and corrections.
Canadian Theses
Author: National Library of CanadaPublisher:
ISBN:
Category : Dissertations, Academic
Languages : en
Pages : 634
Book Description
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Author: 
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