Nuclear Reactor Analysis
-15%
portes grátis
Nuclear Reactor Analysis
Duderstadt, James J.; Hamilton, Louis J.
John Wiley & Sons Inc
01/1976
672
Mole
Inglês
9780471223634
15 a 20 dias
1274
Descrição não disponível.
Part 1: Introductory Concepts Of Nuclear Reactor Analysis
Chapter 1: An Introduction to Nuclear Power Generation 3
Chapter 2: The Nuclear Physics of Fission Chain Reactions 10
Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74
Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor
Chapter 4: Neutron Transport 103
Chapter 5: The One-Speed Diffusion-Theory Model 149
Chapter 6: Nuclear Reactor Kinetics 233
Part 3: The Multigroup Diffusion Method
Chapter 7: Multigroup Diffusion Theory 285
Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315
Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375
Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398
Part 4: An Introduction To Nuclear Reactor-Core Design
Chapter 11: General Aspects of Nuclear Reactor Core Design 447
Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467
Chapter 13: The Calculation of Core Power Distributions 515
Chapter 14: Reactivity Control 537
Chapter 15: Analysis of Core-Composition Changes 566
Appendices
A. Some useful Nuclear Data 605
B. Some useful Mathematical Formulas 611
C. Step Functions, Delta Functions, and Other Exotic Beasts 613
D. Some Properties of Special Functions 616
E. Some Assorted Facts on Linear Operators 621
F. An Introduction to Matrices and Matrix Algebra 626
G. An Introduction to Laplace Transforms 629
H. Typical Nuclear Power Reactor Data 634
I. Units Utilized in Text 636
Index 639
Chapter 1: An Introduction to Nuclear Power Generation 3
Chapter 2: The Nuclear Physics of Fission Chain Reactions 10
Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74
Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor
Chapter 4: Neutron Transport 103
Chapter 5: The One-Speed Diffusion-Theory Model 149
Chapter 6: Nuclear Reactor Kinetics 233
Part 3: The Multigroup Diffusion Method
Chapter 7: Multigroup Diffusion Theory 285
Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315
Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375
Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398
Part 4: An Introduction To Nuclear Reactor-Core Design
Chapter 11: General Aspects of Nuclear Reactor Core Design 447
Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467
Chapter 13: The Calculation of Core Power Distributions 515
Chapter 14: Reactivity Control 537
Chapter 15: Analysis of Core-Composition Changes 566
Appendices
A. Some useful Nuclear Data 605
B. Some useful Mathematical Formulas 611
C. Step Functions, Delta Functions, and Other Exotic Beasts 613
D. Some Properties of Special Functions 616
E. Some Assorted Facts on Linear Operators 621
F. An Introduction to Matrices and Matrix Algebra 626
G. An Introduction to Laplace Transforms 629
H. Typical Nuclear Power Reactor Data 634
I. Units Utilized in Text 636
Index 639
Este título pertence ao(s) assunto(s) indicados(s). Para ver outros títulos clique no assunto desejado.
nuclear; concepts; introductory; part; reactor; introduction; generation; power; reactions; fission chain; physics; reactoran; diffusion; model; diffusiontheory model; multigroup; theory
Part 1: Introductory Concepts Of Nuclear Reactor Analysis
Chapter 1: An Introduction to Nuclear Power Generation 3
Chapter 2: The Nuclear Physics of Fission Chain Reactions 10
Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74
Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor
Chapter 4: Neutron Transport 103
Chapter 5: The One-Speed Diffusion-Theory Model 149
Chapter 6: Nuclear Reactor Kinetics 233
Part 3: The Multigroup Diffusion Method
Chapter 7: Multigroup Diffusion Theory 285
Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315
Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375
Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398
Part 4: An Introduction To Nuclear Reactor-Core Design
Chapter 11: General Aspects of Nuclear Reactor Core Design 447
Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467
Chapter 13: The Calculation of Core Power Distributions 515
Chapter 14: Reactivity Control 537
Chapter 15: Analysis of Core-Composition Changes 566
Appendices
A. Some useful Nuclear Data 605
B. Some useful Mathematical Formulas 611
C. Step Functions, Delta Functions, and Other Exotic Beasts 613
D. Some Properties of Special Functions 616
E. Some Assorted Facts on Linear Operators 621
F. An Introduction to Matrices and Matrix Algebra 626
G. An Introduction to Laplace Transforms 629
H. Typical Nuclear Power Reactor Data 634
I. Units Utilized in Text 636
Index 639
Chapter 1: An Introduction to Nuclear Power Generation 3
Chapter 2: The Nuclear Physics of Fission Chain Reactions 10
Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74
Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor
Chapter 4: Neutron Transport 103
Chapter 5: The One-Speed Diffusion-Theory Model 149
Chapter 6: Nuclear Reactor Kinetics 233
Part 3: The Multigroup Diffusion Method
Chapter 7: Multigroup Diffusion Theory 285
Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315
Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375
Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398
Part 4: An Introduction To Nuclear Reactor-Core Design
Chapter 11: General Aspects of Nuclear Reactor Core Design 447
Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467
Chapter 13: The Calculation of Core Power Distributions 515
Chapter 14: Reactivity Control 537
Chapter 15: Analysis of Core-Composition Changes 566
Appendices
A. Some useful Nuclear Data 605
B. Some useful Mathematical Formulas 611
C. Step Functions, Delta Functions, and Other Exotic Beasts 613
D. Some Properties of Special Functions 616
E. Some Assorted Facts on Linear Operators 621
F. An Introduction to Matrices and Matrix Algebra 626
G. An Introduction to Laplace Transforms 629
H. Typical Nuclear Power Reactor Data 634
I. Units Utilized in Text 636
Index 639
Este título pertence ao(s) assunto(s) indicados(s). Para ver outros títulos clique no assunto desejado.
