Russell / Dunworth Reactor Safeguards

1. Auflage 2013
ISBN: 978-1-4832-8271-8
Verlag: Elsevier Science & Techn.
Format: PDF
Kopierschutz: 1 - PDF Watermark

E-Book, Englisch, 400 Seiten, Web PDF

Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactors, the dispersion of radioactive material, and requirements for reactor sites. The final chapter focuses on operating experience with nuclear reactors. It presents a of history of reactor incidents which are useful to study since much of the knowledge of reactor safety has come from the conscientious reporting of the details and circumstances of failure.

Autoren/Hrsg.

Russell, Charles R.

Dunworth, J. V.

Inhaltsverzeichnis

1;Front Cover;1
2;Reactor Safeguards;4
3;Copyright Page;5
4;Table of Contents;6
5;PREFACE;8
6;FOREWORD;10
7;CHAPTER 1. INTRODUCTION;12
7.1;RADIATION HAZARDS;12
7.2;CHICAGO PILES 1, 2, AND 3;13
7.3;OAK RIDGE;17
7.4;HANFORD;20
7.5;REACTOR SAFEGUARDS COMMITTEE;23
7.6;EXCLUSION DISTANCE FORMULA;23
7.7;NATIONAL REACTOR TESTING STATION;29
7.8;CONTAINMENT;33
7.9;UNIVERSITY RESEARCH REACTORS;33
7.10;POWER REACTORS;35
7.11;REFERENCES;40
8;CHAPTER 2. RADIOACTIVE MATERIALS;41
8.1;REFERENCES;68
9;CHAPTER 3. REACTOR KINETICS;69
9.1;INTRODUCTION;69
9.2;THE INHOUR;81
9.3;RAMP CHANGES IN REACTIVITY;81
9.4;VARIABLE REACTIVITY;82
9.5;THE XENON PROBLEM;83
9.6;FEEDBACK AND STABILITY;88
9.7;CIRCULATING FUEL;94
9.8;REFERENCES;94
10;CHAPTER 4. CONTROL AND SAFETY SYSTEMS;95
10.1;INTRODUCTION;95
10.2;METHODS OF CONTROL;95
10.3;ROD SYSTEMS;96
10.4;CONTROL DRIVE MECHANISMS;98
10.5;BACK-UP SHUTDOWN SYSTEM;105
10.6;REACTOR FUSES AND SAFETY DEVICES;106
10.7;REACTOR PROTECTION SYSTEMS;109
10.8;REACTOR START-UP PROCEDURES;114
10.9;START-UP AFTER CONTROLLED SHUTDOWN;115
10.10;REFERENCES;116
11;CHAPTER 5. CONTAINMENT;117
11.1;INTRODUCTION;117
11.2;MECHANISM OF RELEASE OF RADIOACTIVE MATERIAL;120
11.3;NUCLEAR EXCURSIONS;121
11.4;DISSOLUTION OF FUEL ELEMENTS;125
11.5;METAL-WATER REACTIONS;125
11.6;COMBUSTION OF REACTOR MATERIALS;134
11.7;MELTING OF REACTOR FUELS;139
11.8;SHOCK WAVES;144
11.9;EBWR BLAST SHIELD;147
11.10;EXPERIMENTAL BREEDER REACTOR II BLAST SHIELD;150
11.11;MISSILE PENETRATION;156
11.12;MISSILES FROM ROTATING MACHINERY;160
11.13;SIZE OF BREAK OR LEAKS IN COOLING SYSTEMS;160
11.14;DESIGN OF CONTAINMENT STRUCTURES;162
11.15;REFERENCES;179
12;CHAPTER 6. SAFETY FEATURES OF WATER REACTORS;182
12.1;INTRODUCTION;182
12.2;REACTOR EXPERIMENTS;183
12.3;WATER-COOLED AND MODERATED RESEARCH REACTORS;204
12.4;ZIRCONIUM-HYDRIDE, WATER MODERATED REACTORS;205
12.5;REFERENCES;207
13;CHAPTER 7. DISPERSION OF RADIOACTIVE MATERIAL;208
13.1;INTRODUCTION;208
13.2;PROBLEMS IN ROUTINE OPERATION;208
13.3;DIFFUSION THEORY;220
13.4;NOMOGRAMS FOR GRAPHICAL SOLUTIONS;222
13.5;REFERENCES;234
14;CHAPTER 8. EXTENT OF POSSIBLE DAMAGES;235
14.1;INTRODUCTION;235
14.2;MAXIMUM PERMISSIBLE DOSE;235
14.3;ACUTE NUCLEAR EXPOSUREf;237
14.4;INTERNAL SOURCES OF RADIATIONf;239
14.5;EXPOSURE CALCULATIONS;242
14.6;EVACUATION LIMITS;254
14.7;DIFFUSION, DEPOSITION, AND RAIN-OUT OF THE ACTIVITY;259
14.8;REFERENCES;269
15;CHAPTER 9. SITE REQUIREMENTS;270
15.1;INTRODUCTION;270
15.2;RADIATION EXPOSURE AND SITE CRITERIA;275
15.3;THE SHIPPINGPORT SITE;286
15.4;GENERAL SITE REQUIREMENTS;289
15.5;SPECIAL PROBLEMS;294
15.6;REFERENCES;295
16;CHAPTER 10. OPERATING EXPERIENCE;296
16.1;FUEL ELEMENT FAILURES;296
16.2;CRITICALITY ACCIDENTS—1;297
16.3;CRITICALITY ACCIDENTS—2;298
16.4;CRITICALITY ACCIDENTS—3;299
16.5;CRITICALITY ACCIDENTS—4;300
16.6;CRITICALITY ACCIDENTS—5;301
16.7;CRITICALITY ACCIDENTS—6;302
16.8;CRITICALITY ACCIDENTS—7;305
16.9;CRITICALITY ACCIDENTS—8;305
16.10;CRITICALITY ACCIDENTS—9;308
16.11;CRITICALITY ACCIDENTS—10;309
16.12;CRITICALITY ACCIDENTS—11;313
16.13;CRITICALITY ACCIDENTS—12;314
16.14;ACCIDENT—13;315
16.15;ACCIDENT—14;316
16.16;ACCIDENT—15;317
16.17;ACCIDENT—16;317
16.18;ACCIDENT—17;318
16.19;ACCIDENT—18;319
16.20;ACCIDENT—19;322
16.21;ACCIDENT—20;326
16.22;ACCIDENT—21;327
16.23;ACCIDENT—22;328
16.24;ACCIDENT—23;330
16.25;ACCIDENT—24;331
16.26;ACCIDENT—25;333
16.27;ACCIDENT—26;334
16.28;ACCIDENT—27;335
16.29;REFERENCES;352
17;APPENDIX A: Example of a Calculation of Reactor Siting Distance;354
18;APPENDIX B: Estimates by the Reactor Safeguard Committee of Radiation from a Cloud of Fission Products (Reproduced from "Summary Report of Reactor Safeguard Committee", Wash-3 (Rev.) by permission of the U.S. Atomic Energy Commission);357
19;APPENDIX C: Estimates by the Reactor Safeguard Committee of Radioactive Contamination by Precipitation "Summary Report of Reactor Safeguard Committee," (Reproduced from Wash-3 (Rev.) by permission of the U.S. Atomic Energy Commission);361
20;APPENDIX D: Estimates by the Reactor Safeguards Committee of the Energy Developed in an Exploding Reactor (Reproduced from "Summary Report of the Reactor Safeguard Committee," Wash-3 (Rev.) by permission of the U.S. Atomic Energy Commission);364
21;APPENDIX E: Some Reports to the Atomic Energy Commission by the Advisory Committee on Reactor Safeguards;368
22;INDEX;404