|
|
|
1 | (5) |
|
Atomic and Nuclear Physics |
|
|
5 | (47) |
|
|
|
5 | (2) |
|
Atomic and Nuclear Structure |
|
|
7 | (1) |
|
Atomic and Molecular Weight |
|
|
8 | (3) |
|
|
|
11 | (1) |
|
|
|
11 | (3) |
|
|
|
14 | (1) |
|
Excited States and Radiation |
|
|
15 | (3) |
|
Nuclear Stability and Radioactive Decay |
|
|
18 | (4) |
|
Radioactivity Calculations |
|
|
22 | (4) |
|
|
|
26 | (3) |
|
|
|
29 | (4) |
|
|
|
33 | (4) |
|
Gases, Liquids, and Solids |
|
|
37 | (3) |
|
|
|
40 | (12) |
|
|
|
44 | (1) |
|
|
|
45 | (7) |
|
Interaction of Radiation with Matter |
|
|
52 | (65) |
|
|
|
52 | (2) |
|
|
|
54 | (3) |
|
|
|
57 | (3) |
|
|
|
60 | (2) |
|
Neutron Cross-Section Data |
|
|
62 | (6) |
|
Energy Loss in Scattering Collisions |
|
|
68 | (6) |
|
|
|
74 | (16) |
|
γ-Ray Interactions with Matter |
|
|
90 | (10) |
|
|
|
100 | (17) |
|
|
|
109 | (1) |
|
|
|
110 | (7) |
|
Nuclear Reactors and Nuclear Power |
|
|
117 | (113) |
|
The Fission Chain Reaction |
|
|
117 | (2) |
|
|
|
119 | (10) |
|
Non-Nuclear Components of Nuclear Power Plants |
|
|
129 | (4) |
|
Components of Nuclear Reactors |
|
|
133 | (3) |
|
Power Reactors and Nuclear Steam Supply Systems |
|
|
136 | (49) |
|
|
|
185 | (16) |
|
|
|
201 | (16) |
|
|
|
217 | (2) |
|
Radioactive Waste Disposal |
|
|
219 | (11) |
|
|
|
223 | (1) |
|
|
|
224 | (6) |
|
Neutron Diffusion and Moderation |
|
|
230 | (36) |
|
|
|
230 | (1) |
|
|
|
231 | (4) |
|
The Equation of Continuity |
|
|
235 | (2) |
|
|
|
237 | (1) |
|
|
|
238 | (2) |
|
Solutions of the Diffusion Equation |
|
|
240 | (6) |
|
|
|
246 | (2) |
|
The Group-Diffusion Method |
|
|
248 | (4) |
|
Thermal Neutron Diffusion |
|
|
252 | (5) |
|
Two-Group Calculation of Neutron Moderation |
|
|
257 | (9) |
|
|
|
260 | (1) |
|
|
|
260 | (6) |
|
|
|
266 | (61) |
|
One-Group Reactor Equation |
|
|
266 | (5) |
|
|
|
271 | (3) |
|
|
|
274 | (8) |
|
The One-Group Critical Equation |
|
|
282 | (4) |
|
|
|
286 | (11) |
|
|
|
297 | (11) |
|
|
|
308 | (1) |
|
|
|
309 | (18) |
|
|
|
320 | (1) |
|
|
|
321 | (6) |
|
The Time-Dependent Reactor |
|
|
327 | (76) |
|
Classification of Time Problems |
|
|
328 | (2) |
|
|
|
330 | (18) |
|
Control Rods and Chemical Shim |
|
|
348 | (17) |
|
Temperature Effects on Reactivity |
|
|
365 | (11) |
|
Fission Product Poisoning |
|
|
376 | (13) |
|
Core Properties during Lifetime |
|
|
389 | (14) |
|
|
|
397 | (1) |
|
|
|
398 | (5) |
|
Heat Removal From Nuclear Reactors |
|
|
403 | (63) |
|
General Thermodynamic Considerations |
|
|
404 | (4) |
|
Heat Generation in Reactors |
|
|
408 | (9) |
|
|
|
417 | (11) |
|
Heat Transfer to Coolants |
|
|
428 | (13) |
|
|
|
441 | (9) |
|
Thermal Design of a Reactor |
|
|
450 | (16) |
|
|
|
457 | (2) |
|
|
|
459 | (7) |
|
|
|
466 | (82) |
|
History of Radiation Effects |
|
|
467 | (1) |
|
|
|
468 | (8) |
|
|
|
476 | (3) |
|
The Biological Effects of Radiation |
|
|
479 | (6) |
|
Quantitative Effects of Radiation on the Human Species |
|
|
485 | (10) |
|
Calculations of Radiation Effects |
|
|
495 | (4) |
|
Natural and Man-Made Radiation Sources |
|
|
499 | (7) |
|
Standards of Radiation Protection |
|
|
506 | (5) |
|
Computations of Exposure and Dose |
|
|
511 | (15) |
|
Standards for Intake of Radionuclides |
|
|
526 | (9) |
|
Exposure from γ-Ray Sources |
|
|
535 | (13) |
|
|
|
539 | (3) |
|
|
|
542 | (2) |
|
|
|
544 | (4) |
|
|
|
548 | (64) |
|
Gamma-Ray Shielding: Buildup Factors |
|
|
549 | (10) |
|
Infinite Planar and Disc Sources |
|
|
559 | (7) |
|
|
|
566 | (5) |
|
|
|
571 | (2) |
|
|
|
573 | (3) |
|
Nuclear Reactor Shielding: Principles of Reactor Shielding |
|
|
576 | (2) |
|
|
|
578 | (6) |
|
The Reactor Shield Design: Removal-Attenuation Calculations |
|
|
584 | (4) |
|
The Removal-Diffusion Method |
|
|
588 | (2) |
|
|
|
590 | (5) |
|
|
|
595 | (4) |
|
|
|
599 | (5) |
|
|
|
604 | (8) |
|
|
|
605 | (1) |
|
|
|
606 | (6) |
|
Reactor Licensing, Safety, and The Environment |
|
|
612 | (149) |
|
Governmental Authority and Responsibility |
|
|
613 | (1) |
|
|
|
614 | (9) |
|
Principles of Nuclear Power Plant Safety |
|
|
623 | (8) |
|
Dispersion of Effluents from Nuclear Facilities |
|
|
631 | (19) |
|
Radiation Doses from Nuclear Plants |
|
|
650 | (19) |
|
|
|
669 | (12) |
|
|
|
681 | (20) |
|
|
|
701 | (9) |
|
Environmental Radiation Doses |
|
|
710 | (21) |
|
|
|
721 | (2) |
|
|
|
723 | (8) |
| APPENDIXES |
|
|
I Units and Conversion Factors |
|
|
731 | (6) |
|
II Fundamental Constants and Data |
|
|
737 | (8) |
|
III Vector Operations in Orthogonal Curvilinear Coordinates |
|
|
745 | (6) |
|
IV Thermodynamic and Physical Properties |
|
|
751 | (6) |
|
|
|
757 | (4) |
| Index |
|
761 | |