Nuclear Engineering Handbook (Mechanical and Aerospace Engineering Series)

Nuclear power has, in recent years, undergone a major transformation, resulting in major technical developments and a new generation of nuclear scientists and engineers. A comprehensive book that reflects the latest nuclear technologies has been lacking—until now. The **Nuclear Engineering Handbook is a response to this global resurgence of interest in commercial nuclear power. A broad overview of nuclear power and engineering and their limitless potential, this basic introduction to the field provides an in-depth discussion of power plants and extensive coverage of the nuclear fuel cycle, waste disposal, and related engineering technologies.** Organized into three sections—__Nuclear Power Reactors__, __Nuclear Fuel Cycle Processes and Facilities__, and __Engineering and Analytical Applications__—this book addresses the entire nuclear fuel cycle and process. Topics include everything from the mining, milling, and enrichment of uranium and thorium fuel resources, to fuel fabrication, nuclear materials transportation, fuel reprocessing, and safe waste disposal. This all-encompassing volume discusses current analytical techniques related to nuclear engineering, addressing safety, heat transfer, shielding, thermo-hydraulics, and heat physics. Covering reactor operation and radiation protection, it also outlines the economic considerations involved in building new nuclear power stations instead of large fossil-fueled plants, and elaborates on concerns regarding the control of emissions from the latter. A review of past and current nuclear engineering capabilities, this valuable resource covers the gamut of crucial topics, including historical perspectives, a detailed technological review, and an assessment of the field’s future direction. It is an exceptional tool that will help readers to foster optimal understanding and use of nuclear power for electricity generation now and in the future. Nuclear Engineering Handbook......Page 2 Front Cover......Page 1 Title Page......Page 6 Contents......Page 8 Preface......Page 10 Acknowledgments......Page 14 Editor......Page 16 Contributors......Page 18 Section I Introduction to Section 1: Nuclear Power Reactors......Page 22 1. Historical Development of Nuclear Power......Page 24 1.1.1 BWR Power Plants......Page 25 1.1.4 Organic Cooled and Moderated Reactors......Page 26 1.2 Current Power Reactor Technologies......Page 27 2. Pressurized Water Reactors (PWRs)......Page 30 2.3 The Power Plant......Page 32 2.4 Vendors......Page 33 2.5 General Description of PWR Nuclear Power Plants Presently in Use......Page 34 2.5.2 Control......Page 35 2.5.3 Burnable Poison (BP)......Page 36 2.5.4 Coolant Pumps......Page 38 2.5.6 Pressurizer......Page 39 2.6 Operations......Page 41 2.7.3 Tertiary Loop......Page 45 2.8.2 Grid Assemblies......Page 46 2.8.4 Control Rods......Page 47 2.8.6 Startup......Page 48 2.8.7 Construction Materials......Page 49 2.9.1 Auxiliary Flows......Page 50 2.9.2 Water Sources......Page 51 2.9.3 BTRS......Page 52 2.9.4 Residual Heat Removal System (RHRS)......Page 54 2.9.5 BRS......Page 56 2.10 Engineered Safeguards Systems......Page 57 2.10.1 SIS......Page 58 2.10.2 High-Pressure Injection......Page 59 2.10.3 System Safeguards......Page 60 2.10.4 SIS Components......Page 61 2.10.6 Emergency Feedwater for Secondary Loop......Page 62 2.10.7 Component Cooling Water System (CCWS)......Page 65 2.11 Containment Systems......Page 68 2.11.3 Dead Loads......Page 69 2.11.10 Containment Design Criteria......Page 70 2.11.12 Containment Liner Criteria......Page 71 2.11.15 Containment Isolation System (CIS)......Page 72 2.11.16 Containment Spray System (CSS)......Page 73 2.11.18 RCFC System......Page 74 2.12 Instrumentation......Page 75 2.13.1 Spent Fuel Handling......Page 76 2.14.1 Liquid Waste Processing......Page 77 2.14.3 Solid Waste Processing......Page 78 2.15.1 New PWR Designs......Page 79 2.15.2 Chemical Control of the Coolant System......Page 85 2.15.3 RCP......Page 86 2.15.4 Steam Generator......Page 88 2.15.6 ADS......Page 93 2.15.7 RNS......Page 96 2.16 PXS......Page 97 2.18 IRWST......Page 98 2.19 Safety Design Rationale for Venting the Reactor Vessel Head......Page 100 References......Page 103 3. Boiling Water Reactors (BWRs)......Page 104 3.1.2 BWR-6 Product Line......Page 106 3.1.3 ABWR......Page 107 3.1.5 Summary Description......Page 110 3.2.2 Reactor Assembly......Page 116 3.2.2.1 Reactor Vessel......Page 117 3.2.2.2 Core Shroud......Page 118 3.2.3 Reactor Water Recirculation System......Page 119 3.2.3.1 Jet Pump Assembly......Page 120 3.2.3.2 Operating Principle of the Jet Pump......Page 121 3.2.3.5 Valves and Piping......Page 122 3.2.4 Main Steam Lines......Page 123 3.2.4.1 Safety/Relief Valves......Page 124 3.2.5 Control Rod Drive System......Page 125 3.3.1 Introduction......Page 127 3.3.3 Description of Fuel Assembly......Page 129 3.3.3.2 Design Basis of Fuel Rods......Page 130 3.3.3.3 Fuel Bundle......Page 131 3.3.3.4 Bundle Features......Page 132 3.3.4.2 Axial Distribution......Page 133 3.3.4.6 Thermal-Hydraulic Analysis......Page 134 3.3.4.7.3 Moderator Density Reactivity Coefficient......Page 135 3.3.4.9 Margin between Operating Limits and Damage Limits......Page 136 3.3.4.11 Reactor Stability......Page 137 3.3.5.2 Control Rod Nuclear Characteristics......Page 138 3.4.1 Introduction......Page 139 3.4.2 Reactor Water Cleanup (RWC) System......Page 140 3.4.4 Closed Cooling Water System for Reactor Service......Page 141 3.4.6 SBLC System......Page 142 3.4.7 RCIC System......Page 143 3.4.8 ECCS......Page 144 3.4.8.1 HPCS System......Page 146 3.4.8.2 LPCS System......Page 147 3.4.9.1 LPCI......Page 148 3.5.2 Plant Startup......Page 149 3.5.2.1 Reactor Startup and Operation......Page 150 3.5.3.2 Recirculation Flow Control......Page 151 3.5.3.3 System Control......Page 152 3.5.3.5 Pressure Relief Function......Page 153 3.5.4.1 Source Range Monitor (SRM)......Page 154 3.5.4.3 Local Power Range Monitor (LPRM)......Page 155 3.5.5 Nuclear System Protection System......Page 156 3.5.5.2 Nuclear System Isolation Function......Page 157 3.5.5.7 Backup Protection......Page 158 3.5.6 Rod Control and Information (RC&I)......Page 159 4. Heavy Water Reactors......Page 162 4.1 Introduction......Page 163 4.2 Characteristics of HWRs......Page 164 4.2.1.2.1 Pressure Tubes as the Reactor Pressure Boundary......Page 165 4.2.1.2.4 Moderator Characteristics......Page 166 4.2.1.2.7 Reactivity Control Characteristics......Page 167 4.2.1.2.10 Licensing......Page 168 4.2.1.3.2 Fuel and Fuel Handling System......Page 169 4.2.1.3.3 HTS......Page 171 4.2.1.3.4 Heat Transport Auxiliary Systems......Page 172 4.2.1.3.5 Moderator and Auxiliary Systems......Page 173 4.2.1.3.6 Reactor Regulating System......Page 174 4.2.1.3.7.1 Feedwater and Main Steam System......Page 176 4.2.1.3.7.2 Turbine Generator System......Page 177 4.2.1.3.7.3 Power System Station Services......Page 178 4.2.1.3.7.4 Station Instrumentation and Control......Page 180 4.2.1.4.1 Integrated 4-unit CANDU HWRs......Page 181 4.2.1.4.3 Pressure Tube Boiling Light Water Coolant, Heavy Water Moderated Reactors......Page 182 4.2.2 Characteristics of Pressure Vessel HWRs......Page 184 4.2.2.4.1 Introduction......Page 185 4.2.2.4.4 Lucens Reactor......Page 186 4.2.3.1 Channels with a High-Temperature, High-Pressure Boundary......Page 187 4.2.3.3.1 The EL4 Fuel Channel......Page 190 4.3.1 Purpose of Heavy Water......Page 191 4.3.2 Heavy Water Production......Page 192 4.3.3 Tritium......Page 196 4.4.1 Background......Page 197 4.4.3 Reactor Shutdown......Page 198 4.4.4 Heat Sinks......Page 200 4.4.6 Single-Unit Containment System......Page 201 4.4.7 Multi-Unit Containment System......Page 202 4.4.9 Safety Analysis......Page 203 4.4.10 Safety Analysis Scope......Page 204 4.4.11.1 Small Break LOCA......Page 205 4.4.11.2 Large Break LOCA......Page 206 4.4.11.3 Analysis Methods......Page 207 4.4.12 Severe Accidents......Page 208 4.5.1 Introduction......Page 209 4.5.2.1 Beyond Uranium......Page 211 4.5.3 Two Views of Fuel Cycles: DFC or AFC......Page 214 4.5.3.2 Global Realities and Directions: Emphasis on Nuclear Energy and Fuel Cycles......Page 215 Glossary......Page 216 References......Page 217 5. High-Temperature Gas Cooled Reactors......Page 218 5.1.1 Description of PB-1......Page 219 5.1.2 Fort St. Vrain Description......Page 222 5.1.3 Steam Cycle/Variable Cogeneration (SC/C) HTGR Plant Description (Conceptual Design, Circa 1985)......Page 223 5.2.1 HTGR Type Similarities......Page 224 5.3 HTGR Design Evolution......Page 226 5.3.1 MHTGR Steam Cycle Plant Description (Conceptual Design, Circa 1990)......Page 228 5.3.2 Process Steam/Cogeneration Modular Helium Reactor (PS/C-MHR) Plant Description (Conceptual Design, Circa 1995)......Page 229 5.3.3 GT-MHR Plant Description (Preliminary Design, Circa 2000)......Page 230 5.4.1 GT-MHR Reactor System......Page 232 5.4.2 GT-MHR PCS......Page 234 5.4.3 GT-MHR Heat Removal System......Page 236 5.4.4 GT-MHR Environmental Characteristics......Page 238 5.5.3.2 GT-MHR LEU/Th (single particle) Fuel Cycle......Page 240 5.6.1.1 Alumina Plant......Page 241 5.6.1.2 Coal Gasification......Page 242 5.6.1.5 Hydrogen Production......Page 243 5.6.1.6 Steel Mill......Page 244 5.6.1.8 Research/Test Reactors......Page 245 5.6.3 Sustainability Applications......Page 246 References......Page 247 6. Generation IV Technologies......Page 248 6.1 GFR System......Page 250 6.1.2 GFR Achievement of Generation IV Goals......Page 251 6.2 VHTR......Page 252 6.2.1 VHTR Description......Page 253 6.2.4 VHTR R&D Requirements for Commercial Development......Page 254 6.3.1 SCWR Description......Page 255 6.3.4 SCWR R&D Requirements for Commercial Development......Page 256 6.4.1 SFR Description......Page 257 6.4.4 SFR R&D Requirements for Commercial Development......Page 258 6.5.1 L FR Description......Page 259 6.5.4 L FR R&D Requirements for Commercial Development......Page 260 6.6.1 MSR Description......Page 261 6.6.4 MSR R&D Requirements for Commercial Development......Page 262 Reference......Page 263 Section II Introduction to Section 2: Nuclear Fuel Cycle......Page 264 7.2 Uranium and Depleted Uranium......Page 266 7.3 Uranium Resources......Page 268 7.4 Geology of Uranium Deposits......Page 269 7.5 Mining Techniques......Page 271 7.7 Environmental Aspects of Uranium Mining......Page 272 7.8 Uranium Production......Page 274 7.9 Uranium Market and Prices......Page 280 7.10 Conversion......Page 281 7.11 Thorium......Page 283 8.1.1 Beginning......Page 286 8.2 What is Uranium Enrichment?......Page 287 8.3.2 Electromagnetic Isotope Separation......Page 288 8.3.3.1 Background of Gaseous Diffusion......Page 289 8.3.3.2 Gaseous Diffusion Process......Page 291 8.3.4.1 Background of Gas Centrifuge Enrichment......Page 293 8.3.4.2 Gas Centrifuge Process......Page 294 8.3.5.1 Laser Isotope Background......Page 296 8.3.5.2 Laser Separation Processes......Page 298 8.3.8 Chemical Exchange......Page 299 9.1 Introduction......Page 300 9.2.1 Fuel Pellet Manufacturing......Page 301 9.2.1.1 Uranium Conversion......Page 302 9.2.1.2 Powder Preparation......Page 303 9.2.1.3 Fuel Pellet Processing......Page 304 9.2.2 Fuel Rod Fabrication......Page 305 9.3 Fuel Assembly Component Manufacture......Page 306 9.3.1 Alloy Manufacture......Page 307 9.4 Fuel Facility Licensing......Page 308 9.5 Other Fuel Fabrication Facilities......Page 310 10.1 Introduction......Page 314 10.2 Wet Storage......Page 315 10.2.1 Pressurized Water Reactor (PWR) Spent Fuel Storage Racks......Page 316 10.2.3.1 PWR Racks......Page 317 10.2.3.2 BWR Racks......Page 319 10.2.4 Structural Considerations......Page 320 10.2.5 Thermal Hydraulics Considerations......Page 321 10.2.7 Material Considerations......Page 322 10.3 Dry Cask Storage......Page 323 10.3.2 Types of Dry Storage Casks......Page 325 10.3.4 Structural Considerations......Page 327 10.3.5 Thermal Considerations......Page 328 10.3.6 Shielding Considerations......Page 329 10.3.7 Criticality Considerations......Page 330 10.3.9 Loading Sequence......Page 331 References......Page 333 11. Nuclear Fuel Reprocessing......Page 336 11.1 Objectives, Challenges of Reprocessing......Page 337 11.2 Commercial Reprocessing: History and Current Status......Page 338 11.3 Irradiated Oxide Reactor Fuel–Composition and Chemical State......Page 339 11.4 Evolution of Reprocessing Methods......Page 340 11.4.1.1 Bismuth Phosphate......Page 342 11.4.1.2 Redox Process......Page 343 11.4.1.3 Butex Process......Page 345 11.4.1.5 Thorex......Page 347 11.4.2.1 Volatility Process: Fluoride Volatility......Page 348 11.4.2.2 Pyroprocess......Page 350 11.5.1 Basic Commercial Process: PUREX Process......Page 352 11.5.1.1 Head-End Steps: Receipt and Storage, Shearing, Dissolution, Input Accountancy......Page 353 11.5.1.1.2 Shearing and Dissolution......Page 354 11.5.1.1.3 Separation from Cladding......Page 355 11.5.1.2.1 Separation and Purification—The Aqueous Part......Page 356 11.5.1.2.3 Post-Separation Operations......Page 358 11.5.1.3 Waste Generation and Processing......Page 359 11.5.1.4.1 Solvent Degradation......Page 360 11.5.1.4.2 Off-Gas Treatment......Page 361 11.5.1.4.3 Nitric Acid Recovery......Page 364 11.5.1.5 Theoretical Models: Distribution Equilibria in Aqueous Systems......Page 365 11.5.2.1 UREX......Page 366 11.5.2.2 TRUEX......Page 368 11.5.2.3 DIAMEX......Page 369 11.5.2.4 SANEX......Page 370 11.5.2.6 TALSPEAK......Page 371 11.6.1 Key Distinctions Vis A Vis Aqueous Processing of Fast Reactor Fuels......Page 373 11.6.5 Refabrication of Metal Fuels......Page 374 11.7.1 United States......Page 375 11.7.2 France......Page 376 11.7.4 Russia......Page 377 11.7.5 United Kingdom......Page 378 11.8 Economics......Page 379 References......Page 381 12. Waste Disposal: Transuranic Waste, High-Level Waste and Spent Nuclear Fuel, and Low-Level Radioactive Waste......Page 388 12.1 Introduction......Page 389 12.2 TRU Waste: Case Study of the WIPP......Page 390 12.2.1 Siting......Page 393 12.2.2 Land Withdrawal......Page 394 12.2.3 Construction......Page 395 12.2.4.1 Transportation......Page 396 12.2.4.2 Licensing......Page 398 12.2.4.3 Mixed Wastes and the Complexity of Dual Regulation......Page 399 12.3 HLW and SNF......Page 400 12.3.1 Proposed Repository for HLW......Page 401 12.4.1 Demonstration of Technical Soundness......Page 402 12.4.4 Cultural Issues......Page 403 12.5 Nuclear Power and Public Acceptance......Page 404 12.6.1 Definition of LLRW......Page 405 12.6.2 Classes of LLRW......Page 406 12.6.5 Waste Classification......Page 408 12.6.6 Shipping LLRW......Page 410 12.6.7 LLRW Disposal in the United States......Page 413 12.6.8.1 Performance Objectives (10 CFR 61, Subpart C)......Page 415 12.6.8.2 Site Suitability Requirements (10 CFR 61.50)......Page 416 12.6.8.4 Operating and Closure Requirements (10 CFR 61.52)......Page 417 12.6.8.5 Environmental Monitoring Requirements (10 CFR 61.53)......Page 418 12.6.8.7 Other Requirements......Page 419 References......Page 420 13. Radioactive Materials Transportation......Page 424 13.1 Introduction......Page 425 13.2.2 US DOT......Page 426 13.3.1 Identification......Page 427 13.3.3 Radioactive Material Exemptions......Page 428 13.3.4 Activity Determination in Preparation for Packaging Selection......Page 429 13.4.1 Limited Quantity Material......Page 430 13.4.2 Type A Material......Page 431 13.4.3 Type B Material......Page 432 13.4.4 Fissile Material......Page 433 13.4.5 Low Specific Activity Material......Page 434 13.4.6 SCOs......Page 435 13.4.7 Packaging and Shipping LSA and SCO......Page 436 13.5.2 IP-1......Page 437 13.5.4 IP-3......Page 439 13.5.6 Freight Containers used as IPs......Page 440 13.5.8 Pyrophoric Class 7 Materials......Page 442 13.6.3 Transloading......Page 443 13.6.5 Contamination and Radiation Control......Page 444 13.6.8 Incident Reporting......Page 445 13.7.1 Shipping Documentation......Page 446 13.7.3 Labeling......Page 448 13.8 Highway Route-Controlled Quantities (HRCQ) and Spent Nuclear Fuel......Page 449 13.9 International Shipments......Page 450 References......Page 451 14.1 Background of Decontamination and Decommissioning (D&D)......Page 452 14.2 Phases in the Life of a Site to Which D&D Applies......Page 453 14.3 Establishment of Initial Conditions, Approach, and End State......Page 457 14.4 True Cost of Performing D&D Work......Page 461 14.5 S&M Phase and the Activities Performed to Enhance D&D......Page 462 14.6 Balancing Changing Conditions through D&D......Page 465 14.7 Balancing Changing Cultures......Page 466 14.8 Balancing Planning and Engineering Processes......Page 468 14.9 Tailored (or Graded) Systems Engineering Approach......Page 469 14.10 Balancing the Graded Systems Engineering Design Approach......Page 470 14.11 Choosing Design-Flexible Technologies......Page 472 14.12 Control of Field Work thru Design......Page 473 14.13 Establishment of Project Management Systems......Page 476 14.14 Control Provided by Project Management......Page 480 14.15 Control of Field Work: Integrated Safety Management System (ISMS) and Other Tools......Page 482 14.16 Balancing Worker Selection......Page 484 14.17 Balancing the Execution Approach......Page 486 14.19 Control of Field Work through Construction Management......Page 487 14.20 Balancing Field Execution Processes......Page 490 14.21 Conclusion: The Act of D&D and the Art of Balance......Page 493 15. HWR Fuel Cycles......Page 496 15.1 Natural Uranium Fuel Cycle......Page 497 15.2 Fuel Design......Page 498 15.3 Fuel Performance......Page 500 15.4 Load Following Capability......Page 502 15.7.1 Features Leading to Fuel Cycle Flexibility......Page 503 15.7.2 Fuel Cycle Drivers......Page 507 15.7.3 Flexible Designs for Diverse Fuels......Page 508 15.7.4.2 Indian Experience......Page 509 15.7.4.4 Argentinean Experience: CARA Bundle......Page 510 15.8.1 Introduction......Page 511 15.8.2 Benefits of Enrichment in the HWR......Page 512 15.8.3 Higher Burnup Fuel Design and Performance Experience......Page 514 15.8.4 Mixed Natural Uranium-SEU Core......Page 515 15.8.5.1 Use of SEU in the Advanced CANDU Reactor......Page 516 15.8.5.2 Use of RU in an HWR......Page 517 15.8.5.4 DUPIC Fuel Cycle......Page 518 15.8.5.5 Fuel Design, Fabrication, and Performance......Page 519 15.8.5.6 Reactor Characteristics......Page 520 15.8.6 Burning Thorium......Page 521 15.8.6.1.1 Canadian Experience......Page 523 15.8.6.2.1 Thorium Fuel Fabrication Experience......Page 524 15.8.6.2.3 Thorium Irradiation Experience in Research Reactors......Page 526 15.8.6.2.4 Thorium Irradiation Experience in Power Reactors......Page 527 15.8.6.3.1 OTT Fuel Cycles......Page 528 15.8.6.3.3 Other Recycling Options......Page 530 15.8.6.3.4 SSET Cycle......Page 531 15.8.6.3.6 Pu‐Thorium as a Plutonium-Dispositioning Option......Page 532 15.8.6.3.7 Power Plant Optimization for Thorium Use: The Indian Advanced Heavy Water Reactor (AHWR)......Page 533 15.8.6.4.1 Physical Properties......Page 534 15.9.1 Introduction......Page 535 15.9.3 Dry Storage of Spent HWR Fuel......Page 536 15.9.4 Summary......Page 538 References......Page 539 Section III Introduction to Section 3: Related Engineering and Analytical Processes......Page 544 16.1 Background: Status of Operating Commercial Nuclear Reactors in the United States......Page 546 16.2 NRC Reactor Licensing Process and Required Permits......Page 547 16.2.1 Two-Step Licensing Process (10 CFR Part 50)......Page 550 16.2.3 Early Site Permit (ESP) Process......Page 552 16.2.4 Design Certification......Page 553 16.3.1 Historical Background......Page 554 16.3.2 Scope of PRA......Page 557 16.3.4 Level-II PRA/Back-End Analysis......Page 558 16.3.6 Uses of PRA......Page 560 16.4.1 Aleatory Uncertainty......Page 561 References......Page 562 17. Nuclear Safety of Government Owned, Contractor Operated Nuclear (GOCO) Facilities......Page 564 17.1 Introduction......Page 565 17.2.1 Atomic Energy Act of 1946......Page 566 17.2.3 Price–Anderson Act of 1957......Page 567 17.2.5 DOE Organization Act of 1977......Page 568 17.2.7 Energy Policy Act of 2005 (EPACT)/PAAA of 2005......Page 569 17.3.2 Defense Nuclear Facility Safety Board (DNFSB)......Page 570 17.4.1.1 DOE G 424.1-1A Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements......Page 573 17.4.3 DOE Order 5480.23, Nuclear Safety Analysis Reports......Page 574 17.4.3.2 DOE-STD-3009, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses......Page 575 17.4.3.3 DOE-HDBK-3010 Airborne Release Fractions (ARFS)/Rates and Respirable Fractions (RFs) for Nonreactor Nuclear Facilities......Page 577 17.4.3.6 DOE G 421.1-2, Implementation Guide for Use in Developing Documented Safety Analyses to Meet Subpart B of 10CFR830......Page 578 17.5.1 10 CFR830 Subpart A, QA Requirements......Page 579 17.5.1.2 DOE O 414.1C, QA......Page 580 17.5.2 10 CFR830 Subpart B Safety Basis Requirements......Page 581 17.5.3.2 Operational Procedure, Identifying, Reporting, and Tracking Nuclear Safety Noncompliances (June 1988)......Page 582 17.6 Development of a DOE-STD-3009 DSA......Page 583 References......Page 593 18. Neutronics......Page 596 18.1.1 Neutron Chain Reactions......Page 597 18.1.1.1 Absorption......Page 598 18.1.1.2 Fission......Page 599 18.1.2 Neutron Transport Equation......Page 600 18.1.3 Need for Neutron Distribution Knowledge......Page 601 18.1.4.1 Deterministic Solutions......Page 602 18.1.4.2 Stochastic Solutions......Page 603 18.2.1 General Overview of Reactor Analysis......Page 605 18.2.2 Basic Static Reactor Analysis Approach......Page 606 18.3 Criticality Safety Analysis......Page 615 18.3.1.1 “MAGICMERV”: Physical Parameters Affecting k-Effective......Page 619 18.3.1.2 Parameter-Driven Analysis: Normal Conditions, Contingencies, Controls......Page 620 18.3.2 Second Step: Determination of the Subcriticality of Normal and Contingency States......Page 622 18.3.2.1 Most commonly used computer code systems......Page 624 18.3.2.2 Validation of Calculational Methods......Page 625 18.3.3 Third Step: Translation of Results into Documented Process Controls......Page 627 References......Page 628 19. Radiation Protection......Page 630 19.1.1 Alpha Particles......Page 631 19.1.2 Beta Particles......Page 632 19.1.3 Gamma and X-Rays......Page 633 19.1.3.2 Photoelectric Effect......Page 636 19.1.3.3 Pair Production......Page 637 19.1.4.3 Neutron Absorption......Page 638 19.2.4 Dose Limits......Page 640 19.2.6 As Low As Reasonably Achievable (ALARA)......Page 642 19.2.7.4 ALARA Internal Dose Precautions......Page 643 19.3.1 External Dosimetry......Page 644 19.3.2 Internal Dosimetry......Page 647 19.3.4 Intake Calculation......Page 649 19.3.5 Internal Dose Calculation......Page 651 19.4.1.1 Gamma Shielding......Page 652 19.4.1.1.1 Exponential Attenuation......Page 653 19.4.1.1.2 Geometric Attenuation......Page 654 19.4.1.1.3 Rules of Thumb......Page 655 19.4.1.3 Neutron Shielding......Page 656 19.4.1.4 Shielding Computer Codes......Page 657 19.4.2 PPE......Page 658 19.4.3 Engineered Controls......Page 660 References......Page 661 20. Heat Transfer and Thermal Hydraulic Analysis......Page 662 20.1 Introduction......Page 663 20.2.1 Fission Energy in Reactor......Page 665 20.2.2 Volumetric Heat Generation in Fuel......Page 666 20.2.3 Heat Generation during Transient......Page 667 20.2.3.1 Integrated Beta and Gamma Emission Rates......Page 668 20.2.4.2 Heat Generation from Radiation within the Core......Page 669 20.3.2 General Heat Conduction Equation......Page 670 20.3.2.2 Boundary Conditions......Page 672 20.3.2.3 Initial Condition......Page 674 20.3.3.2 Heat Conduction in a Solid Circular Cylinder with Heat Generation–a Fuel Rod......Page 675 20.3.4 Thermal Properties......Page 676 20.4.1 Introduction......Page 678 20.4.2.1 External Flow......Page 680 20.4.2.2 Internal Flow......Page 682 20.4.3.1 External Flow......Page 685 20.4.3.2 Internal Flow......Page 688 20.5.1 Introduction......Page 691 20.5.2 Flow Patterns......Page 695 20.5.3 Flow Pattern Maps......Page 697 20.5.4 Counter Current Flow and Flooding......Page 699 20.5.5 Flow Models......Page 700 20.5.5.3 Two-Fluid Model......Page 701 20.5.6 Pressure Drop and Pressure Gradient......Page 702 20.5.6.1 HEM Model Pressure Gradient......Page 703 20.5.6.2 Two-Phase Friction Multipliers......Page 704 20.5.7 Choked Flow......Page 705 20.5.8.1 Static Instabilities......Page 709 20.5.8.2 Dynamic Instabilities......Page 710 20.5.8.3 Startup Transients......Page 711 20.6.2.2 Pool Boiling......Page 712 20.6.2.5 Correlations for Boiling Heat Transfer......Page 714 20.6.3 Condensation Heat Transfer......Page 715 20.6.3.1 Film Condensation......Page 718 20.6.3.2 Effect of Non-Condensable Gas......Page 721 20.7.1 Introduction......Page 723 20.7.2 Axial Temperature Distribution Single Phase......Page 724 20.7.3 Two-Phase Heat Transfer......Page 727 20.7.4 Hot Channel and Burnout......Page 728 20.7.5 Thermal-Hydraulics Codes......Page 729 References......Page 730 21.1 Introduction......Page 734 21.2 Theoretical Thermal Efficiency......Page 737 21.3.1.1 Rankine Cycle......Page 739 21.3.1.2 Regenerative Cycle......Page 741 21.3.1.3 Reheat Cycle......Page 742 21.3.2 Gas Turbine Cycle......Page 744 21.3.3 Combined Cycle......Page 745 21.4 Thermal Cycle of Nuclear Power Plant......Page 746 22. Economics of Nuclear Power......Page 748 22.1 History and Promise of Inexpensive Energy......Page 749 22.2.1.1 Experience to Date......Page 751 22.2.1.2 Methods of Financing......Page 754 22.2.1.4 Economy of Size......Page 755 22.2.3 Fuel Costs......Page 756 22.2.3.2 Enriching the Uranium to Higher Content of U-235......Page 757 22.2.3.3 Manufacturing of the Fuel Assembly......Page 758 22.2.3.4 Cost of Fuel per kW Hour......Page 759 22.2.3.6 Government Involvement with Spent Nuclear Fuel......Page 760 22.2.6 Decontamination and Decommissioning......Page 761 22.3.1 Water Availability and Cost......Page 762 22.3.4 Reprocessing vs. Open Fuel Cycle......Page 763 22.3.6 Public Perceptions and Radiation Health Effects......Page 764 22.3.8.2 Underground Siting of Nuclear Power Plant Parks......Page 765 22.4.1 Coal and Coal Gasification......Page 766 22.4.3 Solar Power......Page 767 22.4.5 Backup Power Requirement......Page 768 22.4.7 Future Economically Competitive Potential Applications of Nuclear Energy......Page 769 Index......Page 772 Back Cover......Page 790 Nuclear power has, in recent years, undergone a major transformation, resulting in major technical developments and a new generation of nuclear scientists and engineers. A comprehensive book that reflects the latest nuclear technologies has been lacking—until now. The Nuclear Engineering Handbook is a response to this global resurgence of interest in commercial nuclear power. A broad overview of nuclear power and engineering and their limitless potential, this basic introduction to the field provides an in-depth discussion of power plants and extensive coverage of the nuclear fuel cycle, waste disposal, and related engineering technologies. Organized into three sections— Nuclear Power Reactors , Nuclear Fuel Cycle Processes and Facilities , and Engineering and Analytical Applications —this book addresses the entire nuclear fuel cycle and process. Topics include everything from the mining, milling, and enrichment of uranium and thorium fuel resources, to fuel fabrication, nuclear materials transportation, fuel reprocessing, and safe waste disposal. This all-encompassing volume discusses current analytical techniques related to nuclear engineering, addressing safety, heat transfer, shielding, thermo-hydraulics, and heat physics. Covering reactor operation and radiation protection, it also outlines the economic considerations involved in building new nuclear power stations instead of large fossil-fueled plants, and elaborates on concerns regarding the control of emissions from the latter. A review of past and current nuclear engineering capabilities, this valuable resource covers the gamut of crucial topics, including historical perspectives, a detailed technological review, and an assessment of the field’s future direction. It is an exceptional tool that will help readers to foster optimal understanding and use of nuclear power for electricity generation now and in the future.

jaakko Hintikka Is One Of The Most Creative Figures In Contemporary Philosophy. He Has Made Significant Contributions To Virtually All Areas Of The Discipline, From Epistemology And The Philosophy Of Logic To The History Of Philosophy And The Philosophy Of Science. Part Of The Fruitfulness Of Hintikka’s Work Is Due To Its Opening Important New Lines Of Investigation And New Approaches To Traditional Philosophical Problems. This Volume Gathers Together Essays From Some Of Hintikka’s Colleagues And Former Students Exploring His Influence On Their Work And Pursuing Some Of The Insights That We Have Found In His Work. This Book Includes A Comprehensive Overview Of Hintikka’s Philosophy By Dan Kolak And John Symons And An Annotated Bibliography Of Hintikka’s Work.