Author: K. M. RosePublisher:
ISBN:
Category :
Languages : en
Pages : 11
Book Description
The Axial Distribution of Deformation in the Cladding of PWR Fuel Rods in a Loss-of-coolant Accident
Author: K. M. RoseThe deformation, oxidation and embrittlement of PWR fuel cladding in a loss-of-coolant accident
Author: P.D. ParsonsPublisher:
ISBN: 9780853562085
Category : Metallurgy
Languages : en
Pages : 99
Book Description
Zirconium in the Nuclear Industry: Tenth International Symposium
Author: A. M. GardePublisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805
Book Description
The deformation, oxidation and embrittlement of PWR fuel cladding in a loss-of-coolant accident
Author: P. D. ParsonsPublisher:
ISBN:
Category : Metallurgy
Languages : en
Pages :
Book Description
Nuclear Science Abstracts
Author: 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.
Multiphase Flow Dynamics 4
Author: Nikolay Ivanov KolevPublisher: Springer Science & Business Media
ISBN: 3540929185
Category : Technology & Engineering
Languages : en
Pages : 761
Book Description
The nuclear thermal hydraulic is the science providing knowledge about the physical processes occurring during the transferring the fission heat released in structural materials due to nuclear reactions into its environment. Along its way to the environment the thermal energy is organized to provide useful mechanical work or useful heat or both. Chapter 1 contains introductory information about the heat release in the re- tor core, the thermal power and thermal power density in the fuel, structures and moderator, the influence of the thermal power density on the coolant temperature, the spatial distribution of the thermal power density. Finally some measures are introduced for equalizing of the spatial distribution of the thermal power density. Chapter 2 gives the methods for describing of the steady and of the transient temperature fields in the fuel elements. Some information is provided regarding influence of the cladding oxidation, hydrogen diffusion and of the corrosion pr- uct deposition on the temperature fields. Didactically the nuclear thermal hydraulic needs introductions at different level of complexity by introducing step by step the new features after the previous are clearly presented. The followed two Chapters serve this purpose. Chapter 3 describes mathematically the “simple” steady boiling flow in a pipe. The steady mass-, momentum- and energy conservation equations are solved at different level of complexity by removing one after the other simplifying assu- tions. First the idea of mechanical and thermodynamic equilibrium is introduced.
NUREG/CR.
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 336
Book Description
Author: 
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