Nuclear safety:
Gespeichert in:
| 1. Verfasser: | |
|---|---|
| Format: | Buch |
| Sprache: | English |
| Veröffentlicht: |
Amsterdam [u.a.]
Elsevier
2006
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| Ausgabe: | 1. ed. |
| Schlagworte: | |
| Online-Zugang: | Inhaltsverzeichnis |
| Beschreibung: | XV, 430 S. Ill., graph. Darst. |
| ISBN: | 0750667230 9780750667234 |
Internformat
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| 245 | 1 | 0 | |a Nuclear safety |c Gianni Petrangeli |
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| 264 | 1 | |a Amsterdam [u.a.] |b Elsevier |c 2006 | |
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Datensatz im Suchindex
| _version_ | 1804141005263339520 |
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| adam_text | NUCLEAR SAFETY GIANNI PETRANGELI AMSTERDAM * BOSTON * HEIDELBERG *
LONDON * NEW YORK * OXFORD PARIS * SAN DIEGO * SAN FRANCISCO * SINGAPORE
SYDNEY * TOKYO . ELSEVIER BUTTERWORTH-HEINEMANN IS AN IMPRINF OF
ELSEVIER CONTENTS PREFACE XIII ACKNOWLEDGEMENTS XV CHAPTER 1
INTRODUCTION 1 1-1 OBJECTIVES 1 . 1-2 A SHORT HISTORY OF NUCLEAR SAFETY
TECHNOLOGY 1-2-1 THE EARLY YEARS 2 1-2-2 FROM THE LATE 1950S TO THE
THREE MILE ISLAND ACCIDENT 2 1-2-3 FROM THE THREE MILE ISLAND ACCIDENT ,
, TO THE CHERNOBYL ACCIDENT 7 . 1-2-4 THE CHERNOBYL ACCIDENT AND AFTER
8 REFERENCES 10 - *-^ * S » CHAPTER NOTES 10 CHAPTER 2 INVENTORY AND
LOCALIZATION OF RADIOACTIVE PRODUCTS IN THE PLANT 13 REFERENCES 15
CHAPTER 3 SAFETY SYSTEMS AND THEIR FUNCTIONS 17 3-1 PLANT SYSTEMS 17 ..
3-2 SAFETY SYSTEMS AND ACCIDENTS 18 * 3-3 FUTURE SAFETY SYSTEMS AND
PLANT CONCEPTS 3-3-1 GENERAL REMARKS; 23 * , 3-3-2 SOME PASSIVE SAFETY
SYSTEMS FOR . NUCLEAR PLANTS ., 27 ; 3-3-3 INHERENTLY SAFE SYSTEMS IN
THE : PROCESS INDUSTRIES ,30 , *..;*. REFERENCES. 32 . -; V ; . .
CHAPTER .NOTES.:- 32 . CHAPTER 4 THE CLASSIFICATION OF ACCIDENTS AND A
DISCUSSION OF SOME EXAMPLES 35 M 4-1 CLASSIFICATION 35 ; ,.. 4-2
DESIGN BASIS ACCIDENTS 35. ... . 4-2-1 SOME IMPORTANT DATA FOR ACCIDENT
ANALYSIS 35 4-2-2 EXAMPLE OF A CATEGORY 2 ACCIDENT: SPURIOUS OPENING OF
A PRESSURIZER SAFETY VALVE 40 4-2-3 EXAMPLE OF A CATEGORY 3 ACCIDENT:
INSTANTANEOUS POWER LOSS TO ALL THE PRIMARY PUMPS 41 .--.*. , ** 4-2-4
EXAMPLE OF A CATEGORY 4 ACCIDENT: MAIN STEAM LINE BREAK 43 4 4-2-5
EXAMPLE OF A CATEGORY 4 ACCIDENT: SUDDEN EXPULSION OF A CONTROL ROD FROM
THE CORE; 44 S 4-2-6 EXAMPLE OF A CATEGORY 4 ACCIDENT: BREAK OF THE
LARGEST PIPE OF THE PRIMARY SYSTEM (LARGE LOCA) * 46 4-2-7 EXAMPLE OF
A CATEGORY 4 ACCIDENT: FUEL HANDLING ACCIDENT 47 4-2-8 AREA ACCIDENTS
50 23., VI CONTENTS 4-3 BEYOND DESIGN BASIS ACCIDENTS 51 4-3-1 PLANT
ORIGINATED ACCIDENTS 51 4-3-2 ACCIDENTS DUE TO HUMAN VOLUNTARY ACTIONS
51 4-4 EXTERNAL ACCIDENTS OF NATURAL ORIGIN 51 REFERENCES 51 CHAPTER
NOTES 51 CHAPTER 5 SEVERE ACCIDENTS 53 5-1 EXISTING PLANTS 53 5-2 FUTURE
PLANTS: EXTREME AND PRACTICABLE SOLUTIONS 55 5-3 SEVERE ACCIDENT
MANAGEMENT: THE PRESENT STATE OF STUDIES AND IMPLEMENTATIONS 57 5-4 DATA
ON SEVERE ACCIDENTS 58 5-5 DESCRIPTIONS OF SOME TYPICAL ACCIDENT
SEQUENCES 58 5-5-1 LOSS OF STATION ELECTRIC POWER SUPPLY (TE = TRANSIENT
+ LOSS OF ELECTRICAL SUPPLY) 58 5-5-2 LOSS OF ELECTRIC POWER WITH LOCA
FROM THE PUMP SEALS (SE = SMALL LOCA + LOSS OF ELECTRIC POWER) 61 5-5-3
INTERFACING SYSTEMS LOCA (V) 61 5-5-4 LARGE LOCA WITH FAILURE OF THE
RECIRCULATION (ALFC) 62 5-5-5 SMALL LOCA WITH FAILURE OF THE
RECIRCULATION (SLFC) 62 5-6 SOURCE TERMS FOR SEVERE ACCIDENTS 62
REFERENCES 64 CHAPTER 6 THE DISPERSION OF RADIOACTIVITY RELEASES 65 6-1
THE MOST INTERESTING RELEASES FOR SAFETY EVALUATIONS 65 6-2 DISPERSION
OF RELEASES: PHENOMENA 66 6-3 RELEASE DISPERSION: SIMPLE EVALUATION
TECHNIQUES 70 6-4 FORMULAE AND DIAGRAMS FOR THE EVALUATION OF
ATMOSPHERIC DISPERSION 71 REFERENCE 76 CHAPTER NOTES 76 CHAPTER 7 HEALTH
CONSEQUENCES OF RELEASES 79 7-1 THE PRINCIPLES OF HEALTH PROTECTION AND
SAFETY 79 7-2 SOME QUANTITIES, TERMS AND UNITS OF MEASURE OF HEALTH
PHYSICS 79 7-3 TYPES OF EFFECTS OF RADIATION DOSES AND LIMITS 80 7-4
EVALUATION OF THE HEALTH CONSEQUENCES OF RELEASES 81 7-4-1 EVALUATION OF
INHALATION DOSES FROM RADIOACTIVE IODINE 81 7-4-2 EVALUATION OF DOSES
DUE TO SUBMERSION IN A RADIOACTIVE CLOUD 81 7-4-3 EVALUATION OF THE
DOSES OF RADIATION FROM CAESIUM-137 DEPOSITED ON THE GROUND
( GROUND-SHINE DOSE) 81 7-4-4 EVALUATION OF THE DOSE DUE TO DEPOSITION
OF PLUTONIUM ON THE GROUND 81 7-4-5 INDICATIVE EVALUATION OF LONG
DISTANCE DOSES FOR VERY SERIOUS ACCIDENTS TO NUCLEAR REACTORS 82 7-4-6
DIRECT RADIATION DOSES 82 REFERENCE 83 CHAPTER NOTES 83 CHAPTER 8 THE
GENERAL APPROACH TO THE SAFETY OF THE PLANT-SITE COMPLEX 85 8-1
INTRODUCTION 85 8-2 THE DEFINITION OF THE SAFETY OBJECTIVES OF A PLANT
ON A SITE 85 8-2-1 THE OBJECTIVES AND LIMITS OF RELEASE/DOSE 85 8-3 SOME
PLANT CHARACTERISTICS FOR THE PREVENTION AND MITIGATION OF ACCIDENTS 86
8-4 RADIATION PROTECTION CHARACTERISTICS 86 8-5 SITE CHARACTERISTICS 87
CHAPTER 9 DEFENCE IN DEPTH 89 9-1 DEFINITION, OBJECTIVES, LEVELS AND
BARRIERS 89 9-2 ADDITIONAL CONSIDERATIONS ON THE LEVELS OF DEFENCE IN
DEPTH 89 CONTENTS VII CHAPTER 10 QUALITY ASSURANCE 93 10-1 GENERAL
REMARKS AND REQUIREMENTS 10-2 ASPECTS TO BE UNDERLINED 93 REFERENCE 94
93 CHAPTER 11 SAFETY ANALYSIS 95 95 97 11-1 INTRODUCTION 95. , , . 11-2
DETERMINISTIC SAFETY ANALYSIS 11-3 PROBABILISTIC SAFETY ANALYSIS 11-3-1
EVENT TREES 98 11-3-2 FAULT TREES 99 11-3-3 FAILURE RATES 105 REFERENCES
105 CHAPTER NOTES 105 CHAPTER 12 SAFETY ANALYSIS REVIEW 107 12-1
INTRODUCTION 107 12-2 THE REFERENCE POINTS 107 12-3 FORESEEING POSSIBLE
ISSUES FOR. DISCUSSION 107 12-4 CONTROL IS NOT DISRESPECTFUL 108 12-5
CLARIFICATION IS NOT DISRESPECTFUL 109 12-6 DESIGNER REPORT ,110 ,
12-6-1 INTRODUCTION 110 12-6-2 CONCLUSIONS 110 12-6-3 HYDRODYNAMIC
ASPECTS 110 12-6-4 EFFECTIVE MASS OF OSCILLATING SYSTEM 111 12-6-5
EVALUATION OF FLUID DAMPING 111 12-6-6 VIBRATION ANALYSIS 111 12-7
DISCUSSION 114 REFERENCES 115 CHAPTER NOTES 115 CHAPTER 13
CLASSIFICATION OF PLANT COMPONENTS 117 REFERENCE 118 CHAPTER 14 NOTES ON
SOME PLANT COMPONENTS 119 14-1 REACTOR PRESSURE VESSEL- 119 14-1-1
PROBLEMS HIGHLIGHTED BY OPERATING EXPERIENCE 119 14-1-2 RUPTURE
PROBABILITY OF NON-NUCLEAR VESSELS 120 14-1-3 FAILURE PROBABILITY OF
NUCLEAR VESSELS 122 14-1-4 VESSEL MATERIAL EMBRITTLEMENT DUE TO NEUTRON
IRRADIATION 124 14-1-5 PRESSURIZED THERMAL SHOCK 126 14-1-6 THE REACTOR
PRESSURE VESSEL OF THREE MILE ISLAND 2 126 14-1-7 GENERAL PERSPECTIVE ON
THE EFFECT OF SEVERE ACCIDENTS ON THE PRESSURE VESSEL 127 14-1-8
RECOMMENDATIONS FOR THE PREVENTION OF HYPOTHETICAL ACCIDENTS GENERATED
BY THE PRESSURE VESSEL 128 14-2 PIPING 130 *.-.,:* 14-2-1 EVOLUTION OF
THE REGULATORY POSITIONS 130 ,* 14-2-2 PROBLEMS INDICATED BY EXPERIENCE
130 14-2-3 LEAK DETECTION IN WATER REACTORS 132 14-2-4 RESEARCH
PROGRAMMES ON PIPING 133 14-3 VALVES 134 **. -. , 14-3-1 GENERAL REMARKS
134 14-3-2 SOME DATA FROM OPERATING EXPERIENCE 134 14-3-3 THE MOST
COMMONLY USED TYPES OF VALVE 135 14-3-4 TYPES OF VALVE: CRITICAL AREAS,
DESIGN AND OPERATION 136 14-3-5 VALVE STANDARDS 140 14-4 CONTAINMENT
SYSTEMS 141 REFERENCES * 142 CHAPTER 15 EARTHQUAKE RESISTANCE 145 15-1
GENERAL ASPECTS, CRITERIA AND STARTING DATA 145 15-2 REFERENCE GROUND
MOTION 148 15-3 STRUCTURAL VERIFICATIONS 158 15-3-1 FOUNDATION SOIL
RESISTANCE 158 15-3-2 RESISTANCE OF STRUCTURES 162 REFERENCES 182 , VIII
CONTENTS CHAPTER 16 TORNADO RESISTANCE 185 16-1 THE PHYSICAL PHENOMENON
185 16-2 SCALE OF SEVERITY OF THE PHENOMENON 186 16-3 .DESIGN INPUT DATA
186 REFERENCE 187 CHAPTER 17 RESISTANCE TO EXTERNAL IMPACT 189 17-1
INTRODUCTION 189 17-2 AIRCRAFT CRASH IMPACT 189 17-2-1 EFFECTS OF AN
AIRCRAFT IMPACT 189 17-2-2 OVERALL LOAD ON A STRUCTURE 189 17-2-3
VIBRATION OF STRUCTURES AND COMPONENTS 191 17-2-4 LOCAL PERFORATION OF
STRUCTURES 191 17-2-5 THE EFFECT OF A FIRE 192 17-2-6 TEMPORARY
INCAPACITY OF THE OPERATING PERSONNEL 192 17-3 PRESSURE WAVE 192 17-5
OTHER IMPACTS 193 REFERENCES 194 CHAPTER 18 NUCLEAR SAFETY CRITERIA 195
18-1 GENERAL CHARACTERISTICS 195 18-2 THE US GENERAL DESIGN CRITERIA 195
18-3 IAEA CRITERIA 196 18-4 EUR CRITERIA 196 18-5 OTHER GENERAL CRITERIA
COMPILATIONS 197 REFERENCES 198 CHAPTER NOTES 198 CHAPTER 19 NUCLEAR
SAFETY RESEARCH REFERENCE 199 199 20-3 SOME SIGNIFICANT EVENTS 201
20-3-1 MECHANICAL EVENTS 201 20-3-2 ELECTRICAL EVENTS 202 20-3-3 SYSTEM
EVENTS 202 20-3-4 AREA EVENTS 203 20-3-5 REACTIVITY ACCIDENTS 204 20-3-6
POSSIBLE FUTURE ACCIDENTS 204 20-4 THE INTERNATIONAL NUCLEAR EVENT SCALE
205 REFERENCES 207 CHAPTER 21 UNDERGROUND LOCATION OF NUCLEAR POWER
PLANTS 209 REFERENCES 212 CHAPTER 22 THE EFFECTS OF NUCLEAR EXPLOSIONS
215 22-1 INTRODUCTION 215 22-2 TYPES OF NUCLEAR BOMB 215 22-3 THE
CONSEQUENCES OF A NUCLEAR EXPLOSION 215 22-4 INITIAL NUCLEAR RADIATION
217 22-5 SHOCK WAVE 217 22-6 INITIAL THERMAL RADIATION 218 22-7 INITIAL
RADIOACTIVE CONTAMINATION ( FALLOUT ) 218 22-8 UNDERGROUND NUCLEAR TESTS
218 22-8-1 HISTORICAL DATA ON NUCLEAR WEAPONS TESTS 218 22-8-2 THE
POSSIBLE EFFECTS OF AN UNDERGROUND NUCLEAR EXPLOSION 219 22-8-3 THE
POSSIBLE RADIOLOGICAL EFFECTS OF THE UNDERGROUND TESTS 220 REFERENCES
220 CHAPTER 23 RADIOACTIVE WASTE 221 23-1 TYPES AND INDICATIVE AMOUNTS
OF RADIOACTIVE WASTE 221 23-2 PRINCIPLES 222 REFERENCE 223 CHAPTER 20
OPERATING EXPERIENCE 20-1 INTRODUCTION 201 20-2 PRINCIPAL SOURCES 201
201 CHAPTER 24 FUSION SAFETY REFERENCES 228 225 CONTENTS IX CHAPTER 25
SAFETY OF SPECIFIC PLANTS AND OF OTHER ACTIVITIES 229 . 25-1 BOILING
WATER REACTORS 229 25-2 PRESSURE TUBE REACTORS 231 25-3 GAS REACTORS 231
25-4 RESEARCH REACTORS 232 25-5 SODIUM-COOLED FAST REACTORS 232 25-6
FUEL PLANTS 233 :.:*:..* 25-7 NUCLEAR SEAWATER DESALINATION PLANTS 233
25-8 VVER PLANTS. 234 25-9 SHIP PROPULSION REACTORS 234 25-10 SAFE
TRANSPORT OF RADIOACTIVE S SUBSTANCES 234 : , : 25-11 SAFETY OF
RADIOACTIVE SOURCES AND OF RADIATION GENERATING MACHINES 234 . ,
REFERENCES 235 CHAPTER 26 NUCLEAR FACILITIES ON SATELLITES 237 26-1
TYPES OF PLANT ,237 26-2 POSSIBLE ACCIDENTS AND THEIR CONSEQUENCES 238
REFERENCE 238 CHAPTER 27 ERRONEOUS BELIEFS ABOUT NUCLEAR SAFETY 239
REFERENCES 241 CHAPTER 28 WHEN CAN WE SAY THAT A PARTICULAR PLANT IS
SAFE? 243 CHAPTER 29 THE LIMITS OF NUCLEAR SAFETY: THE RESIDUAL RISK 245
29-1 RISK IN GENERAL 245 29-2 RISK CONCEPTS AND EVALUATIONS ,, . IN
NUCLEAR INSTALLATION SAFETY 245 . 29-2-1 TOLERABLE RISK 2 4 5 29-2-2
RISK-INFORMED DECISIONS 246 29-3 RESIDUAL RISK: THE CONCEPT OF
LOSS-OF-LIFE EXPECTANCY 247 29-4 RISK FROM VARIOUS ENERGY SOURCES 247
29-5 RISK TO VARIOUS HUMAN ACTIVITIES -248. 29-6 ARE THE RISK ANALYSES
OF NUCLEAR POWER PLANTS CREDIBLE? 248 29-7 PROLIFERATION AND TERRORISM ,
250 REFERENCES 250 ADDITIONAL REFERENCES 251 APPENDICES APPENDIX 1 THE
CHERNOBYL ACCIDENT 279 AL-L INTRODUCTION 279, , AL-2 THE REACTOR 279
AL-3 THE EVENT 281 REFERENCES 284 APPENDIX 2 CALCULATION OF THE ACCIDENT
PRESSURE IN A CONTAINMENT 285 A2-1 INTRODUCTION 285 A2-2 INITIAL
OVERPRESSURE 285 A2-3 CONTAINMENT PRESSURE VERSUS TIME 286 A2-3-1
INTRODUCTORY REMARKS 287 A2-3-2 CALCULATION METHOD ! 287 A2-3-3 HEAT
EXCHANGED WITH THE OUTSIDE THROUGH THE METAL CONTAINER 288 A2-3-4 HEAT
RELEASED BY HOT METALS 288 A2-3-5 HEAT EXCHANGED WITH COLD METALS 289
A2-3-6 HEAT EXCHANGED WITH CONCRETE LAYERS 289 A2-3-7 DECAY HEAT 290
A2-3-8 HEAT REMOVED BY THE SPRAY SYSTEM . INTERNAL TO THE CONTAINMENT
.291 A2-3-9 SOLAR HEAT J91 A2-3-10 THERMAL BALANCE IN THE INTERVAL AT
292: - * A2-3-11 CONSIDERATIONS ON THE PERFORMANCE OF THE CALCULATION
AND OH THE CHOICE OF THE INPUT DATA 292 A2-3-12 EXAMPLE CALCULATION 293
* REFERENCES 296 X CONTENTS APPENDIX 3 TABLE OF SAFETY CRITERIA 297
APPENDIX 4 DOSE CALCULATIONS 315 A4-1 INTRODUCTION 315 A4-2 VIRTUAL
POPULATION DOSE IN A SEVERE ACCIDENT 315 A4-2-1 THE REACTOR AND THE
RELEASED ISOTOPES 315 A4-2-2 SOURCE TERM AT THREE DAYS (L.CS, XE) 315
A4-2-3 DOSE AT THE FENCE AFTER THREE DAYS OF EXPOSURE 316 A4-2-4 GROUND
SHINE LONG-TERM DOSE 316 A4-3 EXPLORATIVE EVALUATION OF THE RADIOLOGICAL
CONSEQUENCES OF A MECHANICAL IMPACT ON A SURFACE STORAGE FACILITY FOR
CATEGORY 2 WASTE 316 A4-3-1 TYPE OF REPOSITORY 316 A4-3-2 REFERENCE
IMPACT 316 A4-3-3 FRAGMENTATION AND DISPERSION OF MATERIAL 317 A4-3-4
DOSES 318 A4-3-5 CONCLUSIONS 319 A4-4 EXPLORATIVE EVALUATION OF THE
RADIOLOGICAL CONSEQUENCES OF A MECHANICAL IMPACT ON A TRANSPORT/STORAGE
CASK CONTAINING SPENT FUEL 319 A4-4-1 CHARACTERISTICS OF THE CASK 319
A4-4-2 REFERENCE IMPACT 319 A4-4-3 AMOUNT OF SIGNIFICANT FISSION
PRODUCTS IN THE INTERNAL ATMOSPHERE OF THE CASK AND EXTERNAL RELEASE IN
ONE DAY 319 A4-4-4 EFFECTIVE COMMITTED DOSES 320 A4-4-5 CONCLUSIONS 321
REFERENCES 321 APPENDIX 5 SIMPLIFIED THERMAL ANALYSIS OF AH
INSUFFICIENTLY REFRIGERATED CORE A5-1 ANALYSIS OF THE CORE WITHOUT
REFRIGERATION 323 A5-2 OTHER FORMULAE AND USEFUL DATA FOR THE INDICATIVE
STUDY OF THE COOLING OF A CORE AFTER AN ACCIDENT 325 REFERENCES 326 323
APPENDIX 6 EXTRACTS FROM EUR CRITERIA (DECEMBER 2004) 327 2-1-8-3 LIST
OF DESIGN BASIS CONDITIONS 327 2-1-8 TABLES 328 2-1-8-1 TABLE 1:
RADIOLOGICAL CRITERIA FOR RADIOACTIVE RELEASES IN NORMAL OPERATION AND
INCIDENT CONDITIONS 328 2-1-8-2 TABLE 2: FREQUENCIES AND ACCEPTANCE
CRITERIA FOR NORMAL OPERATION, INCIDENT AND ACCIDENT CONDITIONS 328
2-1-B-L CRITERIA FOR LIMITED IMPACT FOR DEC 329 2-1-B1-1 TABLE BL:
CRITERIA FOR LIMITED IMPACT FOR NO EMERGENCY ACTION BEYOND 800 M FROM
THE REACTOR 329 2-1B 1-2 TABLE B2: CRITERIA FOR LIMITED IMPACT FOR NO
DELAYED ACTION BEYOND 3 KM FROM THE REACTOR 330 2-1B 1-3 TABLE B3:
CRITERIA FOR LIMITED IMPACT FOR NO LONG-TERM ACTIONS BEYOND 800 M FROM
THE REACTOR 330 2-1B 1-4 TABLE B4: CRITERIA FOR LIMITED IMPACT FOR
ECONOMIC IMPACT 330 2-1 B2 RELEASE TARGETS FOR DESIGN BASIS CATEGORY 3
AND 4 CONDITIONS 330 2-1-B-2-1 TABLE B5: DBA RELEASE TARGETS FOR NO
ACTION BEYOND 800 M FROM THE REACTOR 331 2-1-B-2-2 TABLE B6: DBA RELEASE
TARGETS FOR ECONOMIC IMPACT 331 2-1-2-3 OPERATIONAL STAFF DOSES DURING
NORMAL OPERATION AND INCIDENTS 331 2-1-2-6 PROBABILISTIC SAFETY TARGETS
332 2-1-3-4 SINGLE FAILURE CRITERION 332 2-1-4-3-2 COMPLEX SEQUENCES
THAT MAY BE CONSIDERED IN DEC 333 2-1-6-8 CLASSIFICATION OF THE SAFETY
FUNCTIONS AND CATEGORISATION OF THE EQUIPMENT 333 2-1-6-6-3 REQUIREMENTS
ACCORDING TO LEVEL OF SAFETY FUNCTIONS 334 2-1-6-8-4 ASSIGNMENT OF
EQUIPMENT AND STRUCTURES TO A SAFETY CATEGORY 334 CONTENTS XI 2-1-6-8-5
REQUIREMENTS ON EQUIPMENT AND. , STRUCTURES ACCORDING,TO SAFETY CATEGORY
335 2-1-6-8-6 CLASSIFICATION OF STRUCTURES AND EQUIPMENT ACCORDING TO
THE DESIGN AND CONSTRUCTION CODES 335 2-1-6-8-7 THE RELATION OF SEISMIC
CATEGORISATION TO SAFETY LEVEL OF FUNCTIONS 335 2-1-6-13 ACCIDENT
MANAGEMENT 335 2-1-6-14 RADIATION PROTECTION 336 APPENDIX 7 NOTES ON
FRACTURE MECHANICS A7-1 INTRODUCTION 337 .*..., A7-2 CURRENT PRACTICE
338 REFERENCES 341, 337 APPENDIX 8 US GENERAL DESIGN CRITERIA 343 A8-1
INTRODUCTION 344 A8-2 DEFINITIONS AND EXPLANATIONS 345 A8-3 CRITERIA
345 A8-3-1 OVERALL REQUIREMENTS 345 A8-3-2 PROTECTION BY MULTIPLE
FISSION PRODUCT BARRIERS 346 A8-3-3 PROTECTION AND REACTIVITY CONTROL
SYSTEMS 348 A8-3-4 FLUID SYSTEMS 349 A8-3-5 REACTOR CONTAINMENT 351
A8-3-6 FUEL AND RADIOACTIVITY CONTROL 352 NOTES 353 APPENDIX 9 IAEA
CRITERIA 355 APPENDIX 10 PRIMARY DEPRESSURIZATION SYSTEMS A10-1 INITIAL
STUDIES 357 A10-2 DEPRESSURIZATION SYSTEMS FOR MODERN DESIGN REACTORS
359 REFERENCES 363 357 APPENDIX 11 THERMAL-HYDRAULIC TRANSIENTS OF THE
PRIMARY SYSTEM 365 , AL 1-1 GENERAL REMARKS 365 ALL-2 GENERAL PROGRAM
CHARACTERISTICS 366 ALL-3 PROGRAM DESCRIPTION 366 AL 1-3-1 MACRO STAMPA
DATI 366 AL 1-3-2 MACRO COPIQ_DATI 3,68 AL 1-3-3 MACRO//S 368 ALL-3-4-
MACRO HFG 369 * S: AL 1-3-5,:. MACRO; VF-, 369 * ALLR3-6 MACRO, VFG
370- . ALL-3-7 MACRO QS 370,, AL 1-3-8 MACRO GU 370, S , , AL 1-3-9
MACRO, GE 372 AL 1-3-10 MACRO DT 373 AL 1-3-11 MACRO PS 373 AL 1-4 USING
THE PROGRAM 377 ALL-5 OTHER FORMULAE FOR THE EXPANDED ,%,. . USE OF THE
PROGRAM 377 ALL-5-1 ATWS 377 AL 1-5-2 PRESSURE IN A
DEPRESSURIZATION WATER DISCHARGE TANK 378. REFERENCES 378 * ,. . ., , *,
*; APPENDIX 12 THE ATMOSPHERIC DISPERSION OF RELEASES 379 APPENDIX 13
REGULATORY FRAMEWORK AND SAFETY DOCUMENTS 385 A13-1 REGULATORY FRAMEWORK
385 A13-2 SAFETY DOCUMENTS 385 A13-2-1 THE SAFETY REPORT 386 A13-2-2 THE
PROBABILISTIC SAFETY ASSESSMENT 388 A13-2-3 THE ENVIRONMENTAL IMPACT
ASSESSMENT 388 A13-2-4 THE EXTERNAL EMERGENCY PLAN 388 A13-2-5 THE
OPERATION MANUAL, INCLUDING THE EMERGENCY PROCEDURES 388 A13-2-6
OPERATION ORGANIZATION DOCUMENT 390 A13-2-7 THE PRE-OPERATIONAL TEST
PROGRAMME 390 XII CONTENTS A13-2-8 THE TECHNICAL SPECIFICATIONS FOR
OPERATION 390 A13-2-9 THE PERIODIC SAFETY REVIEWS 391 REFERENCES 391
APPENDIX 14 USNRC REGULATORY GUIDES AND STANDARD REVIEW PLAN 393 A14-1
EXTRACTS FROM A REGULATORY GUIDE 393 A14-2 LIST OF CONTENTS AND EXTRACTS
FROM A SAMPLE CHAPTER OF THE STANDARD REVIEW PLAN 395 A14-3 SAMPLE
CHAPTER 400 APPENDIX 15 SAFETY CAGE 405 A15-1 GENERAL REMARKS 405 A15-2
AVAILABLE ENERGY 405 A15-3 MECHANICAL ENERGY WHICH CAN BE RELEASED 405
A15-4 OVERALL SIZING OF A STRUCTURAL CAGE AROUND THE PRESSURE VESSEL 406
A15-5 EXPERIMENTAL TESTS ON STEEL CAGES FOR THE CONTAINMENT OF VESSEL
EXPLOSIONS 408 REFERENCE 408 APPENDIX 16 CRITERIA FOR THE SITE CHART
(ITALY) 409 A16-1 POPULATION AND LAND USE 409 A16-2 GEOLOGY, SEISMOLOGY
AND SOIL MECHANICS 409 A16-3 ENGINEERING REQUIREMENTS 410 A16-4 EXTREME
EVENTS FROM HUMAN ACTIVITIES 410 A16-5 EXTREME NATURAL EVENTS 410
APPENDIX 17 THE THREE MILE ISLAND ACCIDENT 411 A17-1 SUMMARY DESCRIPTION
OF THE THREE MILE ISLAND NO. 2 PLANT 411 A17-2 THE ACCIDENT 413 A17-3
THE CONSEQUENCES OF THE ACCIDENT ON THE OUTSIDE ENVIRONMENT 419 A17-4
THE ACTIONS INITIATED AFTER THE ACCIDENT 421 REFERENCES 422 GLOSSARY 423
WEB SITES 425 INDEX 427
|
| any_adam_object | 1 |
| author | Petrangeli, Gianni |
| author_facet | Petrangeli, Gianni |
| author_role | aut |
| author_sort | Petrangeli, Gianni |
| author_variant | g p gp |
| building | Verbundindex |
| bvnumber | BV035983589 |
| classification_tum | NUC 640f |
| ctrlnum | (OCoLC)288954662 (DE-599)BVBBV035983589 |
| dewey-full | 621.48 |
| dewey-hundreds | 600 - Technology (Applied sciences) |
| dewey-ones | 621 - Applied physics |
| dewey-raw | 621.48 |
| dewey-search | 621.48 |
| dewey-sort | 3621.48 |
| dewey-tens | 620 - Engineering and allied operations |
| discipline | Energietechnik, Energiewirtschaft Energietechnik |
| edition | 1. ed. |
| format | Book |
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| id | DE-604.BV035983589 |
| illustrated | Illustrated |
| indexdate | 2024-07-09T22:08:59Z |
| institution | BVB |
| isbn | 0750667230 9780750667234 |
| language | English |
| oai_aleph_id | oai:aleph.bib-bvb.de:BVB01-018877491 |
| oclc_num | 288954662 |
| open_access_boolean | |
| owner | DE-91G DE-BY-TUM |
| owner_facet | DE-91G DE-BY-TUM |
| physical | XV, 430 S. Ill., graph. Darst. |
| publishDate | 2006 |
| publishDateSearch | 2006 |
| publishDateSort | 2006 |
| publisher | Elsevier |
| record_format | marc |
| spelling | Petrangeli, Gianni Verfasser aut Nuclear safety Gianni Petrangeli 1. ed. Amsterdam [u.a.] Elsevier 2006 XV, 430 S. Ill., graph. Darst. txt rdacontent n rdamedia nc rdacarrier Centrales nucléaires - Mesures de sécurité ram Centrales nucléaires - Sécurité - Mesures Génie nucléaire - Sécurité - Mesures Kernreaktorsicherheit (DE-588)4144208-8 gnd rswk-swf Kernreaktorsicherheit (DE-588)4144208-8 s DE-604 HEBIS Datenaustausch application/pdf http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=018877491&sequence=000001&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA Inhaltsverzeichnis |
| spellingShingle | Petrangeli, Gianni Nuclear safety Centrales nucléaires - Mesures de sécurité ram Centrales nucléaires - Sécurité - Mesures Génie nucléaire - Sécurité - Mesures Kernreaktorsicherheit (DE-588)4144208-8 gnd |
| subject_GND | (DE-588)4144208-8 |
| title | Nuclear safety |
| title_auth | Nuclear safety |
| title_exact_search | Nuclear safety |
| title_full | Nuclear safety Gianni Petrangeli |
| title_fullStr | Nuclear safety Gianni Petrangeli |
| title_full_unstemmed | Nuclear safety Gianni Petrangeli |
| title_short | Nuclear safety |
| title_sort | nuclear safety |
| topic | Centrales nucléaires - Mesures de sécurité ram Centrales nucléaires - Sécurité - Mesures Génie nucléaire - Sécurité - Mesures Kernreaktorsicherheit (DE-588)4144208-8 gnd |
| topic_facet | Centrales nucléaires - Mesures de sécurité Centrales nucléaires - Sécurité - Mesures Génie nucléaire - Sécurité - Mesures Kernreaktorsicherheit |
| url | http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=018877491&sequence=000001&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA |
| work_keys_str_mv | AT petrangeligianni nuclearsafety |