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Nuclear Reactor Analysis.pdf
July 14, 2008 · Filed Under Engineering Physic · Tags: Chain-Reactions, Core-Thermalhydraulics, Multigroup-Analysis, Nuclear-Energy, Nuclear-Physics, Reactor-Design, Reactor-Statics-&-Kinetics, Training-Material
This is one of the Engineering Physics course material held by nuceng.ca, about introduction to nuclear energy, nuclear physics and chain reactions, reactor statics and kinetics, multigroup analysis, core thermalhydraulics and reactor design.
Contents along with the download links:
- Introduction
- Basic definitions and perspectives [ The Life and Times of the Neutron ~ 1/E Spectrum ~ Decay ~ Cross Section ~ Nuclear Reactions ~ Summary ~ A Look Ahead ]
- One Speed Diffusion - Fixed Sources [ Why Diffusion ~ Interaction Rates and Neutron Flux ~ Neutron Current Density ~ Equation of Continuity ~ Fick's Law ~ Question: What about the Conservation of Momentum and Energy? ~ The Diffusion Equation ~ Boundary Conditions for the Steady State Diffusion Equation ~ Elementary Solutions of the Steady State Diffusion Equation ~ Diffusion Length ]
- Process Modelling [ Estimating a parameter from its current value and its slope ~ Rate equations ~ Steady state ~ Stiff Systems ~ Final words ]
- Numerical Methods [ Estimating a parameter from its current value and its slope ~ Rate equations ~ Steady state ~ Stiff Systems ~ Final words ]
- Chain Reactions [ The Multiplication Factor, k ~ The Four Factor Formula and the Neutron Life Cycle ~ Conversion and Breeding ~ Typical Spectra ~ Control of the Chain Reaction ]
- One Group Diffusion - Reactors [ The One Group Model ~ Relating k to the Criticality Condition ~ Analytical Solution for the Transient case ~ Criticality ~ Criticality for General Bare Geometries ~ Reflected Reactor Geometries ~ Reactor Criticality Calculations ]
- McMaster Nuclear Reactor
- Core Composition Changes [ Fission Product Poisoning ~ Fuel Depletion ]
- Multigroup Theory [ Why We Need the Multigroup Model ~ The Multigroup Equations ~ Generating the Coefficients ~ Simplifications ~ Criticality ~ Group Collapsing ]
- Kinetics [ Point Kinetics Equations ~ Prompt Effects ~ Inverse Method ~ Multigroup Diffusion with Delayed Precursors ]
- Heat Transfer [ General Heat Conduction Equation ~ Definitions and Assumptions ~ Radial Heat Transfer ~ General Thermal Energy Equation ]
- Summary [ Summary of the General Diffusion Based Equations ~ Transient Modelling ]
- Feedback [ Reactivity coefficients ]
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Thanks a lot for your document. I’m a student. I’m researching a bout Nuclear Reactor. I want to know how many kind of Nuclear Reactor. Could you please send to me more document about them?