Nuclear reactor theory and design
By: Roger A. Rydin.
Series: PBS series in reactor physics
Publisher: University Publications
Published: 1977
Place of publication: Blacksburg, Va
Language: eng
Number of pages: 385
Subjects: Nuclear reactors; Nuclear reactors -- Design and construction
Description: Table of Contents																														Page


CHAPTER 1	INTRODUCTION						  1

1.1	Background                                	      1
1.2	Historical Approach					           2
			1.3	Neutron Density						      5
			1.4	Reaction Rates						           6
			1.5	Design Approximations					     11
1.6	Reactor Design Implications				     12

CHAPTER 2	INTERACTIONS OF NEUTRONS 
			WITH MATTER						 17

2.1	Compound Nucleus - Cross Sections		          17
2.2	Nuclear Systematics of Naturally Occurring 
     Isotopes	                    				23
			2.3	Level Widths and Partial Cross Sections			25
2.3	Cross Section for Formulation of the Compound 
     Nucleus						               26
2.5	Reaction Probabilities	     				28
			2.6	Kinematics in the Center-of-Mass System	          30
2.7	Relationships Between the Scattering 
	Angles in the LAB and CM Systems			     36

CHAPTER 3	NUCLEAR FISSION					 45

3.1	Binding Energy					 	          45
3.2	Liquid Drop Model of Fission				     48
3.3	Fission Product Yields					     55
			3.4	Fission Neutron Spectrum				          57
3.5	Prompt Neutrons						     59
3.6	Delayed Neutrons						     62
3.7	Energy Production in Fission				     64

CHAPTER 4	DERIVATION OF THE NEUTRON 
			DIFFUSION EQUATION				 69

4.1	Fick's Law Derivation of the Diffusion Equation   69
4.2*	The One-Speed Transport Equation	     	 	74
4.3*	One-Dimensional, One-Speed Transport Equation     80
4.4*	Derivation of the P1 Equations			          86
4.5	The P1 Diffusion Theory Approximation		     89
4.6	Comments on the P1 Equations of Diffusion Theory  92
4.7*	Alternate Derivation of the Diffusion Equation    94






CHAPTER 5	ANALYTIC SOLUTIONS TO THE 
			ONE-SPEED DIFFUSION EQUATION		 99

5.1	Partial Currents and the Extrapolated Boundary 
     Condition				                    	99
5.2	Source Plane Boundary Conditions		         107
5.3	Two Region Planar Problem				    111
5.4	Point and Line Sources					    113
5.5	Solution to the Inhomogeneous Source Problem	    120
5.6*	General Derivation of the Green's Function	
     Superposition Integral					    123
5.7	Diffusion Length					         126
5.8	Critical Reactors						    128
5.9	Homogeneous Bare Critical Slab Reactor		    131
5.10	Two Region Slab Reactor					    135
5.11	One-Dimensional Bare Homogeneous Cylindrical 				Reactor							         138
5.12	Bare Homogeneous Spherical Reactor			    141
5.13	Comments on Multi-region One-Dimensional 
     Reactors							         145
5.14	Multidimensional Reactors				    149
5.15*	Diffusion Length Experiment				    152

CHAPTER 6	FEW-GROUP EQUATIONS AND 
			NUMERICAL SOLUTION METHODS		165

6.1	Energy-Dependent Diffusion Equation			165
6.2	Few-Group Diffusion Equations				     167
6.3	Finite Difference Few-Group Equations in 
	One Dimension						          172
6.4	Specification of Boundary Conditions		     180
6.5	Direct Solution of the Source Problem		     182
6.6*	Iterative Solution of the Source Problem		187
6.7	Iterative Solution of the Critical Reactor
	Problem							          193
6.8*	Convergence of the Outer Iteration to the
	Fundamental Mode Solution				     198
6.9	Qualitative Comparison Between One-Speed
	and Two-Group Solutions					     202

CHAPTER 7	PERTURBATION THEORY				211

7.1	Adjoint Equations						     211
7.2	Matrix Form of the Adjoint Equations		     217
7.3	First-Order Perturbation Theory			     220
7.4*	Perturbation Effects on Higher Harmonic 
	Modes								     224
7.5	Control Rod Worth						     226
7.6*	Inhomogeneous Case					          230





CHAPTER 8	REACTOR KINETICS					239

8.1	Multigroup Reactor Kinetics Equation		     240		
8.2	Interpretation of Spatial Kinetics Results	     246
8.3	Point Kinetics Equations				          249
8.4	Results for One Group of Delayed Neutrons		255
8.5	Experimental Measurement of Control Rod Worth	261
8.6*	"Point" Kinetics Equations Derivation		     263
8.7	Method of Obtaining   and  			     267

CHAPTER 9	POISONING, TEMPERATURE EFFECTS, 
			AND DEPLETION IN REACTORS			275

9.1	The Fission Product Xenon-135				     276
9.2	Xenon Poisoning						     277
9.3	General Transient Solution for Buildup 
	of Xenon and Iodine					          279
9.4	Spatial Xenon Transients				          283
9.5	Xenon-Induced Spatial Power Oscillations		284
9.6	Samarium Poisoning					          289
9.7	Temperature Effects on Reactivity			     293
9.8	Effect of Thermal Feedback on Reactor Kinetics	297
9.9	Depletion							          308

CHAPTER 10	NEUTRON MODERATION				 321

10.1	Scattering Collisions					     322
10.2	Slowing Down Problem					     329
10.3	Slowing Down in Hydrogen With No Absorption		330
10.4	The Slowing Down Density in Hydrogen, 
	No Absorption						          333
10.5	Moderation for A > 1, No Absorption			335
10.6	Asymptotic Slowing Down Theory, A > 1, 
	No Absorption						          339
10.7*	Slowing Down in Hydrogen With Absorption		343
10.8*	Special Cases of Slowing Down With 
	Absorption, A > 1						     347
10.9	Final Comments            				     353

CHAPTER 11	SLOWING DOWN IN THE PRESENCE 		
			OF RESONANCES					 357

11.1	Resonance Cross Sections				          358
11.2	Doppler Effect						          365
11.3	Slowing Down in the Presence of Resonances	     373
11.4	Homogeneous-Medium Resonance Absorption		     376	
11.5	Homogeneous Resonance Integrals			     385
11.6*	Heterogeneous System Resonance Absorption		391
11.7	Reactor Design Implications of 
	Heterogeneous Lumping					     407
11.8	The GAM Multigroup Slowing Down Equations		412




CHAPTER 12	THERMALIZATION					429

12.1	Neutron Balance Equation				          430
12.2*	Monatomic Gas Moderator Cross Sections		     432
12.3	Solution to the Monatomic Gas 
	Thermalization Problem					     443
12.4	General Case Solution					     446
12.5	Spatial Effects in the Thermalization 
	Problem							          451


APPENDIX A.		THE SINGULARITY FUNCTIONS		461

APPENDIX B.		THE LAPLACE TRANSFORM		465

APPENDIX C.		MATRIX RELATIONSHIPS			473

APPENDIX D.		SPHERICAL HARMONICS			479

APPENDIX E.		DIFFERENTIATION OF AN 
				INTEGRAL						483

INDEX										485
Notes: Includes bibliographies and index. Third edition available from author in pdf form, rar@virginia.edu
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