| Preface to the First Edition |
|
xiii | |
| Preface to the Second Edition |
|
xiv | |
|
Introduction and Review of the Nuclear Fuel Cycle |
|
|
1 | (20) |
|
|
|
1 | (1) |
|
Nuclear Reactor Types---First Generation |
|
|
2 | (5) |
|
Advanced Fission Reactor Designs |
|
|
7 | (6) |
|
|
|
13 | (3) |
|
|
|
16 | (3) |
|
Glossary of Nuclear Fuel Terms |
|
|
19 | (1) |
|
|
|
20 | (1) |
|
Nuclear Fuel Resources, Mining, and Milling |
|
|
21 | (31) |
|
|
|
21 | (1) |
|
Uranium Exploration Techniques |
|
|
22 | (6) |
|
|
|
22 | (1) |
|
|
|
23 | (1) |
|
|
|
24 | (1) |
|
|
|
25 | (1) |
|
|
|
26 | (1) |
|
|
|
27 | (1) |
|
|
|
28 | (1) |
|
Recovery of Uranium from Phosphate and Other By-Product Materials |
|
|
28 | (1) |
|
Principal Uranium-Bearing Minerals |
|
|
28 | (1) |
|
|
|
29 | (6) |
|
|
|
29 | (1) |
|
|
|
30 | (2) |
|
In Situ Leaching (Solution Mining) |
|
|
32 | (1) |
|
Uranium Mines in the United States |
|
|
33 | (2) |
|
The Milling of Uranium Ore |
|
|
35 | (1) |
|
|
|
35 | (6) |
|
Uranium Reserves and Resources |
|
|
41 | (2) |
|
|
|
43 | (2) |
|
Economic Considerations of Uranium Production Methods |
|
|
45 | (3) |
|
Thorium Minerals and Estimates of Reserves |
|
|
48 | (1) |
|
|
|
49 | (3) |
|
|
|
49 | (1) |
|
|
|
49 | (3) |
|
Conversion and Enrichment |
|
|
52 | (25) |
|
|
|
52 | (1) |
|
|
|
53 | (1) |
|
Conversion of Uranium to Uranium Hexafluoride |
|
|
53 | (3) |
|
Enrichment of Uranium by Gaseous Diffusion |
|
|
56 | (4) |
|
Quantitative Aspects of Gaseous Diffusion |
|
|
60 | (4) |
|
The United States Enrichment Corporation (USEC) |
|
|
64 | (1) |
|
Enrichment of Uranium by the Centrifuge Method |
|
|
65 | (2) |
|
Enrichment of Uranium by the Separation Nozzle Method |
|
|
67 | (2) |
|
Enrichment of Uranium by the AVLIS Method |
|
|
69 | (2) |
|
Enrichment Prices and Contracts |
|
|
71 | (3) |
|
|
|
74 | (3) |
|
|
|
74 | (1) |
|
|
|
74 | (3) |
|
Reactor Fuel Design and Fabrication |
|
|
77 | (28) |
|
|
|
77 | (1) |
|
Reactor Fuel and Cladding Materials |
|
|
78 | (6) |
|
|
|
78 | (1) |
|
|
|
79 | (2) |
|
|
|
81 | (1) |
|
Burnable Absorbers or Burnable Poisons |
|
|
82 | (2) |
|
|
|
84 | (11) |
|
|
|
84 | (2) |
|
|
|
86 | (2) |
|
Fuel Element Assembly for a PWR |
|
|
88 | (2) |
|
Fuel Element Assembly for a BWR |
|
|
90 | (3) |
|
Fuel Assembly Identification Scheme |
|
|
93 | (2) |
|
LWR Fuel Problems and Improvements |
|
|
95 | (3) |
|
|
|
95 | (1) |
|
|
|
96 | (1) |
|
|
|
96 | (1) |
|
Axial and Radial Blankets |
|
|
97 | (1) |
|
Examination of Irradiated Fuel for Defects---Fuel Sipping |
|
|
97 | (1) |
|
Other Types of Power Reactor Fuels |
|
|
98 | (4) |
|
The Gas-Cooled Reactor GT-MHR Fuel |
|
|
98 | (2) |
|
|
|
100 | (1) |
|
|
|
101 | (1) |
|
|
|
102 | (1) |
|
|
|
102 | (3) |
|
|
|
103 | (1) |
|
|
|
103 | (2) |
|
Reactor Physics Calculations |
|
|
105 | (60) |
|
|
|
105 | (2) |
|
The Neutron Transport Equation |
|
|
107 | (26) |
|
General Comments About the Neutron Transport Equation |
|
|
107 | (2) |
|
The Diffusion Approximation |
|
|
109 | (1) |
|
The Multigroup Diffusion Equations |
|
|
110 | (5) |
|
Criticality Calculations Using the Multigroup Equations |
|
|
115 | (2) |
|
One- and Two-Group Diffusion Equation Calculations |
|
|
117 | (4) |
|
Numerical Solution of the Multigroup Equations |
|
|
121 | (3) |
|
The Transport Approximations PN and SN |
|
|
124 | (3) |
|
|
|
127 | (1) |
|
|
|
128 | (5) |
|
Nuclear Cross-Section Data |
|
|
133 | (8) |
|
|
|
133 | (1) |
|
Information Contained in ENDF/B |
|
|
134 | (2) |
|
Calculation of the Neutron Energy Spectrum ø(E) |
|
|
136 | (3) |
|
|
|
139 | (2) |
|
Fundamentals of Reactor Reload Calculations |
|
|
141 | (24) |
|
Objectives of Reload Calculations |
|
|
141 | (2) |
|
Calculation of the Average Power per Assembly |
|
|
143 | (2) |
|
Fuel Depletion Calculations |
|
|
145 | (4) |
|
Burnable Poison Calculations |
|
|
149 | (5) |
|
|
|
154 | (5) |
|
|
|
159 | (3) |
|
|
|
162 | (3) |
|
|
|
165 | (45) |
|
|
|
165 | (3) |
|
The Multibatch Core Loading |
|
|
168 | (8) |
|
Burnup, Availability, and Capacity Factors |
|
|
168 | (2) |
|
The Reactivity of the Core |
|
|
170 | (2) |
|
|
|
172 | (2) |
|
|
|
174 | (2) |
|
|
|
176 | (12) |
|
|
|
179 | (1) |
|
|
|
180 | (1) |
|
|
|
180 | (4) |
|
Gas Turbine-Modular Helium Reactor (GT-MHR) Fuel Loading |
|
|
184 | (4) |
|
Extended Burnup and Longer Cycle Length |
|
|
188 | (7) |
|
Effect of Extended Burnup on Fuel Performance |
|
|
188 | (1) |
|
Effect of Extended Burnup on Uranium Needed and on Enrichment |
|
|
189 | (1) |
|
Other Effects Due to Higher Burnup |
|
|
190 | (1) |
|
Effects of Fuel Cycle Length |
|
|
190 | (1) |
|
The Effect of NWPA on Extended Burnup |
|
|
191 | (3) |
|
Fuel Cycle Stretchout (Coastdown) |
|
|
194 | (1) |
|
Burnup Measurement Techniques |
|
|
195 | (1) |
|
|
|
195 | (15) |
|
Planning for a Refueling Outage |
|
|
196 | (2) |
|
|
|
198 | (1) |
|
New Fuel Design Activities |
|
|
199 | (1) |
|
|
|
200 | (2) |
|
|
|
202 | (1) |
|
|
|
203 | (1) |
|
Radiation Exposure During Refueling |
|
|
204 | (1) |
|
|
|
205 | (2) |
|
|
|
207 | (3) |
|
Reprocessing and Recycling |
|
|
210 | (30) |
|
What Is Reprocessing and Recycling? |
|
|
210 | (1) |
|
An Historical Perspective |
|
|
210 | (3) |
|
Why Consider Reprocessing and Recycling? |
|
|
213 | (2) |
|
|
|
215 | (7) |
|
|
|
215 | (1) |
|
|
|
216 | (1) |
|
Proliferation-Resistant Processes |
|
|
217 | (1) |
|
Reprocessing by the Pyrometallurgical Process |
|
|
218 | (1) |
|
Accountability of Reprocessing Plants |
|
|
218 | (2) |
|
Reprocessing Experience in the United States |
|
|
220 | (1) |
|
Reprocessing Experience Outside the United States |
|
|
220 | (2) |
|
Plutonium and Uranium Recycling in LWRs |
|
|
222 | (13) |
|
Materials Flow with Recycling |
|
|
222 | (1) |
|
Uranium Savings Due to Uranium and Plutonium Recycling |
|
|
223 | (3) |
|
SWU Savings Due to Uranium and Plutonium Recycling |
|
|
226 | (1) |
|
Characteristics of Cores with MOX Fuel |
|
|
227 | (3) |
|
Problems with Recycled Uranium |
|
|
230 | (2) |
|
Problems with Recycled Plutonium |
|
|
232 | (2) |
|
Experience with MOX Fuel Used in LWRs |
|
|
234 | (1) |
|
Factors Affecting Implementation of Reprocessing and Recycling |
|
|
235 | (5) |
|
|
|
236 | (2) |
|
|
|
238 | (2) |
|
Utility and Nuclear Power Economics |
|
|
240 | (35) |
|
General Comments and Definitions |
|
|
240 | (10) |
|
Capital and Business Activities |
|
|
240 | (1) |
|
The Engineer's Role in Business |
|
|
240 | (1) |
|
|
|
241 | (1) |
|
|
|
242 | (1) |
|
|
|
243 | (2) |
|
The Time Value or the Present Worth of Money |
|
|
245 | (3) |
|
|
|
248 | (2) |
|
The Utility Industry as a Business |
|
|
250 | (3) |
|
Major Characteristics of Utilities |
|
|
250 | (1) |
|
The Utility Regulatory System |
|
|
251 | (1) |
|
The Effects of Load Demand Variation |
|
|
252 | (1) |
|
The Special Features of Nuclear Fuel |
|
|
253 | (2) |
|
|
|
253 | (1) |
|
The Investment in Nuclear Fuel as a Function of Time |
|
|
254 | (1) |
|
Leasing or Buying Nuclear Fuel |
|
|
254 | (1) |
|
Calculation of the Cost of Electricity |
|
|
255 | (13) |
|
Nuclear Power Plant Construction Costs |
|
|
255 | (3) |
|
Approximate Calculation of the Cost of Electricity |
|
|
258 | (1) |
|
The Levelized Cost of Electricity |
|
|
259 | (4) |
|
Comments on the Levelized Cost Equation |
|
|
263 | (4) |
|
The Levelized Cost of Electricity over a Period of Time |
|
|
267 | (1) |
|
Final Comments and Conclusions |
|
|
268 | (2) |
|
|
|
270 | (5) |
|
|
|
271 | (1) |
|
|
|
272 | (3) |
|
High-Level Waste Management |
|
|
275 | (56) |
|
|
|
275 | (2) |
|
Classification of Radioactive Wastes |
|
|
277 | (2) |
|
Sources and Examples of Radioactive Wastes |
|
|
279 | (1) |
|
The Nuclear Waste Policy Act of 1982 and Its 1987 Amendments |
|
|
279 | (5) |
|
|
|
284 | (16) |
|
|
|
284 | (6) |
|
Radioactivity from Spent Fuel |
|
|
290 | (2) |
|
Decay Heat Generated by Spent Fuel |
|
|
292 | (6) |
|
Spent Fuel Management Outside the United States |
|
|
298 | (2) |
|
Disposal of High-Level Wastes and Transuranic Wastes |
|
|
300 | (18) |
|
Characteristics of High-Level Waste |
|
|
300 | (2) |
|
Characteristics of Transuranic Waste |
|
|
302 | (3) |
|
Solidification of HLW and TRU |
|
|
305 | (3) |
|
|
|
308 | (3) |
|
Geologic Repository Features |
|
|
311 | (5) |
|
The Waste Isolation Pilot Plant |
|
|
316 | (1) |
|
HLW Programs Outside the United States |
|
|
317 | (1) |
|
Transportation of Radioactive Materials |
|
|
318 | (13) |
|
Transportation Regulation |
|
|
318 | (1) |
|
Definitions and Classifications |
|
|
319 | (4) |
|
Testing of Shipping Casks for Spent Nuclear Fuel |
|
|
323 | (3) |
|
|
|
326 | (1) |
|
|
|
326 | (3) |
|
|
|
329 | (2) |
|
Low-Level Waste Management and Decommissioning of Nuclear Power Plants |
|
|
331 | (23) |
|
Sources of Low-Level Wastes |
|
|
331 | (1) |
|
The Low Level Radioactive Waste Policy Act of 1980 and Its 1985 Amendments |
|
|
332 | (3) |
|
|
|
334 | (1) |
|
|
|
335 | (9) |
|
|
|
335 | (1) |
|
Classification of LLW into A, B, and C Classes |
|
|
336 | (3) |
|
Disposal Requirements for Class A, B, and C Wastes |
|
|
339 | (1) |
|
|
|
339 | (1) |
|
|
|
340 | (1) |
|
|
|
340 | (1) |
|
LLW Disposal Programs Outside the United States |
|
|
341 | (3) |
|
Decommissioning of Nuclear Power Plants |
|
|
344 | (6) |
|
|
|
344 | (1) |
|
|
|
345 | (1) |
|
Radioactive Materials Involved in Decommissioning |
|
|
346 | (1) |
|
|
|
346 | (1) |
|
Financing and Cost of Decommissioning |
|
|
347 | (1) |
|
Decommissioning Experience |
|
|
348 | (2) |
|
|
|
350 | (4) |
|
|
|
351 | (1) |
|
|
|
352 | (2) |
|
Environmental Effects of Electricity Generation |
|
|
354 | (23) |
|
|
|
354 | (1) |
|
Various Types of Electricity Generating Systems and Their Environmental Effects |
|
|
355 | (9) |
|
|
|
355 | (1) |
|
|
|
356 | (6) |
|
|
|
362 | (1) |
|
|
|
362 | (1) |
|
|
|
363 | (1) |
|
|
|
363 | (1) |
|
Less Developed Potential Electrical Power Sources |
|
|
364 | (1) |
|
Nuclear Power Plants and Their Environmental Effects |
|
|
364 | (4) |
|
|
|
368 | (7) |
|
|
|
375 | (2) |
|
|
|
375 | (2) |
| Index |
|
377 | |
