Nuclear Reactor Physics 3rd Edition by Weston M. Stacey- Ebook PDF Instant Download/Delivery: 3527413669, 978-3527413669
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Product details:
ISBN 10: 3527413669
ISBN 13: 978-3527413669
Author: Weston M. Stacey
The third, revised edition of this popular textbook and reference, which has been translated into Russian and Chinese, expands the comprehensive and balanced coverage of nuclear reactor physics to include recent advances in understanding of this topic.
The first part of the book covers basic reactor physics, including, but not limited to nuclear reaction data, neutron diffusion theory, reactor criticality and dynamics, neutron energy distribution, fuel burnup, reactor types and reactor safety.
The second part then deals with such physically and mathematically more advanced topics as neutron transport theory, neutron slowing down, resonance absorption, neutron thermalization, perturbation and variational methods, homogenization, nodal and synthesis methods, and space-time neutron dynamics.
For ease of reference, the detailed appendices contain nuclear data, useful mathematical formulas, an overview of special functions as well as introductions to matrix algebra and Laplace transforms.
With its focus on conveying the in-depth knowledge needed by advanced student and professional nuclear engineers, this text is ideal for use in numerous courses and for self-study by professionals in basic nuclear reactor physics, advanced nuclear reactor physics, neutron transport theory, nuclear reactor dynamics and stability, nuclear reactor fuel cycle physics and other important topics in the field of nuclear reactor physics.
Table of contents:
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Neutron Chain Fission Reactors
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Neutron Diffusion and Transport Theory
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Neutron Diffusion and Migration Lengths
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Integral Transport Theory
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Interface Current Methods in Slab Geometry
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Coordinates
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Iterative Solution Procedure
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Neutron Slowing Down
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Reflected Reactor
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Forward Elimination – Backward Substitution Spatial Solution
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Transport Methods
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Neutron Energy Distribution
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Nuclear Reactor Dynamics
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Source Jerk Method
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Fuel Burnup
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Supercritical Water Reactors (SCWR)
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Transient Analyses
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Reactor Safety
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Reactor Accidents
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Resonance Absorption
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Neutron Thermalization
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Calculation of the Thermal Neutron Spectra in Homogeneous Media
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Multigroup Calculation
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Appendices
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Some Useful Mathematical Formulas
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Some Properties of Special Functions
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