Neutronic Analysis For Nuclear Reactor Systems
Häftad, Engelska, 2018
1 999 kr
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Produktinformation
- Utgivningsdatum2018-06-28
- Mått155 x 235 x undefined mm
- FormatHäftad
- SpråkEngelska
- Antal sidor551
- FörlagSpringer International Publishing AG
- ISBN9783319827063
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Dr. Bahman Zohuri is founder of Galaxy Advanced Engineering, Inc. a consulting company that he formed upon leaving the semiconductor and defense industries after many years as a Senior Process Engineer for corporations including Westinghouse and Intel, and then as Senior Chief Scientist at Lockheed Missile and Aerospace Corporation. During his time with Westinghouse Electric Corporation, he performed thermal hydraulic analysis and natural circulation for Inherent Shutdown Heat Removal System (ISHRS) in the core of a Liquid Metal Fast Breeder Reactor (LMFBR). While at Lockheed, he was responsible for the study of vulnerability, survivability and component radiation and laser hardening for Defense Support Program (DSP), Boost Surveillance and Tracking Satellites (BSTS) and Space Surveillance and Tracking Satellites (SSTS). He also performed analysis of characteristics of laser beam and nuclear radiation interaction with materials, Transient Radiation Effects in Electronics (TREE), Electromagnetic Pulse (EMP), System Generated Electromagnetic Pulse (SGEMP), Single-Event Upset (SEU), Blast and, Thermo-mechanical, hardness assurance, maintenance, and device technology. His consultancy clients have included Sandia National Laboratories, and he holds patents in areas such as the design of diffusion furnaces, and Laser Activated Radioactive Decay. He is the author of several books on nuclear engineering heat transfer.
- Neutron Physics Background.- Modeling Neutron Transport and Interactions.- Spatial Effects in Modeling Neutron Diffusion – One Group Models.- Energy Effects in Modeling Neutron Diffusion – Two Group Models.- Numerical Methods in Modeling Neutron Diffusion.- Slowing Down Theory.- Resonance Processing.- Heterogeneous Reactors and Wigner Seitz Cells.- Thermal Spectra and Thermal Cross Sections.- Perturbation Theory for Reactor Neutronics.- Reactor Kinetics and Point Kinetics.- Reactor Dynamics.- Reactor Stability.- Numerical Modeling for Time Dependent Problems.- Fission Product Buildup and Decay.- Fuel Burnup and Fuel Management.- Appendix A: Laplace Transforms.- Appendix B: Transfer Functions and Bode Plots.- Index.
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