|
| 編輯推薦： |
本书为高温气冷堆核电站领域目前为止全球z具权威性、先进性，甚至唯1的综述性专著。
其主要内容依托清华大学核研院牵头组织的10兆瓦高温堆实验堆的设计、研制与实施，此项目为国家重大科技专项，国家863项目之一。
高温气冷堆具有良好的固有安全特性，是目前世界上比较先进的商用反应堆，在国家能源战略中具有重要地位。中国的高温气冷堆技术研究及应用，处于世界领x水平，对全球能源领域有多方面重要影响。
本书为读者深入了解高温气冷堆的原理、技术发展状况、安全特性和潜在的应用领域提供了详尽阐述和充实资料 ，可为从事高温气冷堆技术领域工作的科研开发人员、项目管理人员以及政府官员全面了解高温气冷堆提供参考。
|
| 目錄：
|
1 General Aspects of High-Temperature Reactors .................... 1
1.1 Overview ................................................. 1
1.2 FutureSustainableEnergyTechnologies .......................... 2
1.3 PrincipleCharacteristicsofHTR ................................ 4
1.4 ApplicationofModularHTRintheEnergyEconomy ............... 8
1.5 SafetyAspectsofModularHTR ................................ 10
1.6 FuelCyclesofModularHTR .................................. 11
1.7IntermediateandFinalStorage .............................. 13
1.8OverviewontheHTR-PMProject .............................. 13
1.9 OverviewontheHTRDevelopmentuptoNow .................... 20
References ....................................................... 21
2 Physical Aspects of Core Layout .............................. 23
2.1Overview on Physical Aspects of Core Layout and Design ofModularHTRPlants....................................... 23
2.2SomeAspectsofCriticality................................. 27
2.3In.uence of Re.ectors ....................................... 31
2.4Coef.cientsofReactivity .................................. 33
2.4.1 PrincipleConsideration ............................... 33
2.4.2 Temperature Coef.cients.............................. 34
2.5Demand of Reactivity Compensation and Worth of Control Systems .... 38
2.6Fast Neutron Doses on Re.ectors ............................. 43
2.7In.uenceofFlowofBalls,ActionontheBurnupofFuel ............ 46
2.8Distributions of Fuel, Neutron Flux, and Power Density intheReactorCore .......................................... 52
2.9PrinciplesofKineticsofNuclearReactors .................... 54
2.9.1 OverviewonSomeGeneralAspects ..................... 54
2.9.2 KineticEquations.................................... 58
2.9.3 Simple Solutions of the Kinetic Equations.... .... ..... .... 60
2.10 ProgramSystemsforPhysicalLayoutoftheCore .................. 61
2.10.1GeneralRemarks .................................... 61
2.11 AspectsofCoreLayoutandDesign ............................. 67
2.11.1General Overview and Aspects of Core and Fuel Element Design............................................ 67
2.11.2Discussions on Different Core Parameter . .... .... ..... 69
2.12Physical Aspect of the First Loading and Running in Period ofaPebbleCore ............................................ 74
2.13 DischargingofPebble-BedCores ............................... 80
References ....................................................... 80
3 Thermo-Hydraulic Aspects of Core Layout ......................... 83
3.1 HeatProductionInsidetheCore ................................ 83
3.2 ThermalPoweroftheCore.................................... 87
3.3 DataoftheCoolantGasHelium .......................... 88
L
LL Contents
3.4 Basic Equations of the Thermo-Hydraulics of the Core . .... ..... .... 90
3.5 HeatingupofHeliumCoolantintheCore ........................ 94
3.6Temperature Pro.lesinFuelElements ........................... 98
3.7HeatTransferinthePebble-BedCore............................ 102
3.8Pressure Drops in the Core and Re.ectorStructures ................. 104
3.9Special Aspects of Thermo-Hydraulic Layout of the Core of Modular HTR..................................................... 107
3.9.1 MixingofHotGasBehindtheCore ..................... 107
3.9.2 In.uenceofBypassesontheCoreCooling ................ 110
3.9.3 Uncertainties of Calculation of Power Density and Other Thermo-HydraulicParameters .......................... 111
3.9.4 MeasurementofFuelTemperature....................... 112
3.9.5 c HeatingofCoreInternalsandCooling .................. 113
3.10 PrincipleofCoreLayout...................................... 114
3.11 Comparison of Data of Core Cooling in Some HTR Concepts ..... .... 117
3.12Comparison of Thermo-Hydraulic Aspects of Different ReactorTypes .............................................. 118 References ....................................................... 119
4 Fuel Elements.................................................... 121
4.1 DescriptionoftheComponent ................................. 121
4.2 AspectsofLayoutandDesignofHTRFuelElements ............... 123
4.3 Temperature Distributions in HTR Fuel Elements.. .... .... ..... .... 128
4.4 IrradiationBehaviorofFuelElements............................ 130
4.5 StressesinFuelElements ..................................... 134
4.6 CorrosionofFuelElements.................................... 138
4.7 Fission Product Release from Fuel Elements in Normal Operation .. .... 141
4.8DifferentTypesofSphericalFuelElements ....................... 150
4.9Some Further Experiences with HTR Fuel Elements.... .... ..... .... 151
4.10 ComparisonofLWRandHTRFuelElements ..................... 157
References ....................................................... 161
5 Reactor Components .............................................. 163
5.1 OverviewontheComponents .................................. 164
5.2 InternalReactorStructures .................................... 165
5.2.1 OverviewontheComponents .......................... 165
5.2.2 TechnicalAspectsofCoreInternals...................... 165
5.2.3 LoadsonCoreInternals............................... 175
5.2.4 GraphiteandItsIrradiationBehavior ..................... 178
5.2.5 Results of Analysis of Re.ector Structures During Operation .......................................... 183
5.3 PrimaryEnclosure ........................................... 186
5.3.1 Overview .......................................... 186
5.3.2 Aspects of Dimensioning and Materials for Pressure VesselsofPrimaryCircuit ............................. 189
5.3.3 Neutron Irradiation of Reactor Pressure Vessel andDesignAspects .................................. 197
5.3.4 ActivationoftheReactorPressureVessel ................. 201
5.4 Comparison of Different Reactor Pressure Vessles . .... .... ..... .... 203
5.5 ShutdownandControlSystems................................. 203
5.5.1 OverviewonReactivityAspects ........................ 203
5.5.2 WorthesofShutdownSystemsinHTR ................... 206
5.5.3 Technical Concepts of Control and Shutdown Systems ... .... 208
5.6 FuelHandlingSystem ........................................ 217
ContentsLLL
5.6.1 Overview .......................................... 217
5.6.2 Technical Aspects of the Fuel Handling System ... ..... .... 220
5.6.3 AlternativesfortheFuelHanding ....................... 226
5.6.4 SomeSpecialAspectsofFuelHandling .................. 231
5.7 Measurement Installations for Core Parameters .... .... .... ..... .... 233
5.7.1 MeasurementofNeutronFlux .......................... 233
5.7.2 Measurements of the Thermo-Hydraulic Parameters oftheCore......................................... 236 References ....................................................... 238
6 Components of the Helium Cycle .................................... 241
6.1 Overview ................................................. 241
6.2 HotGasDuct .............................................. 245
6.2.1 DescriptionoftheComponent .......................... 245
6.2.2 TechnicalAspects ................................... 250
6.3 SteamGenerator ............................................ 257
6.3.1 GeneralDescriptionoftheComponent ................... 257
6.3.2 Thermo-HydraulicAspects............................. 267
6.3.3 PressureDrops ...................................... 273
6.3.4 FlowStabilityoftheSteamGenerator .................... 276
6.3.5 Aspects of Mechanical Design of Steam Generator Tubes . .... 278
6.3.6 Experiences with Steam Generators of Gas-Cooled Reactors........................................... 283
6.4 HeliumCirculator ........................................... 290
6.4.1 Overview Some Thermosdynamic Aspects ... .... ..... .... 290
6.4.2 Aspects of Technology of Helium Circulators . .... ..... .... 296
6.4.3 ConceptsofHeliumCirculators ......................... 298
6.5 Gas Puri.cationPlant ........................................ 306
6.5.1 Overview .......................................... 306
6.5.2 Concept of the Gas Puri.cation......................... 311
6.5.3 Experiences with Gas Puri.cationPlants .................. 314
6.6 HeliumCircuitsforDecayHeatRemoval ......................... 316
6.7 HeliumAuxiliarySystems .................................... 320
6.7.1 Overview .......................................... 320
6.7.2 AuxiliaryHeliumCircuits ............................. 320
6.7.3 MeasurementsinHeliumCircuits ....................... 322
6.8 ReactorProtectionSystem .................................... 326
References ....................................................... 327
7 Reactor Containment Building ...................................... 331
7.1GeneralRemarksandRequirements ............................. 331
7.2Aspects of LWR and HTR Containments or Containment Buildings .... 334
7.3Several Overview on Concepts of Reactor Containment Buildings forHTR .................................................. 336
7.4Overview on HTR Containments and Buildings Applied Until Now .... 337
7.5 PlanningWorkfortheContainmentsinthePast.................... 339
References ....................................................... 345
8 Power Conversion Cycle ........................................... 347
8.1 OverviewonFlowSheet...................................... 347
8.2 SomeThermodynamicAspectsoftheSteamCycle ................. 348
8.3 AspectsofSteamTurbine ..................................... 354
8.4 CondensationandCoolingSystems ............................. 356
8.5 Feed Water Preheating System and Feed Water Pumps . .... ..... .... 365
8.6 OptimizationoftheSteamCycle ............................... 368
LY Contents
8.7 PotentialofSteamCycles ..................................... 371
8.8 CogenerationProcessesUsingSteamCycle ....................... 376
References ....................................................... 380
9 Operational Aspects............................................... 381
9.1 Overview on Requirements and Conditions of Plant Operation..... .... 381
9.2 BurnupofFuelandProductionofHigherIsotopes.................. 384
9.2.1 BurnupofFuel ..................................... 384
9.2.2 ProductionofHigherIsotopes .......................... 387
9.3 FissionProductInventory ..................................... 388
9.4 DynamicalEquationsfortheTotalPlant.......................... 395
9.4.1 PrincipleOverview .................................. 395
9.4.2 SystemoftheDynamicalEquations...................... 395
9.4.3 Program Systems for Evaluation of Dynamical Questions . .... 400
9.5 ApplicationsoftheDynamicalEquations ......................... 402
9.6 ConceptofControlandOperationofaModularHTR ............... 405
9.6.1 ConceptofControl .................................. 405
9.6.2 OperationofHTR ................................... 407
9.7 Xenon Dynamics and In.uenceofSamariumonReactivity ........... 411
9.8 DecayHeatRemovalDuringNormalOperation .................... 418
9.8.1 DecayHeatProduction ............................... 418
9.8.2 PrinciplesofDecayHeatRemoval ...................... 419
9.8.3 Decay Heat Removal in a Modular HTR During Normal Operation .......................................... 421
9.9 Release of Radioactive Substances During Normal Operation. ..... .... 423
9.10 AspectsofWasteManagementinModularHTR ................... 426
References ....................................................... 433
10 Safety Aspects and Analysis of Accidents ............................. 435
10.1 GeneralRemarks............................................ 436
10.2 OverviewonRelevantAccidents ............................... 444
10.3 LossofCoolantAccidents .................................... 449
10.4 TotalFailureoftheActiveDecayHeatRemoval ................... 450
10.4.1Decay Heat Production and Active Decay Heat Removal . .... 450
10.4.2Overview Over Different Cases of Loss of Active Decay HeatRemoval ...................................... 453
10.4.3Self-acting Decay Heat Removal Under Full Helium Pressure ........................................... 454
10.4.4The Concept of Self-acting Decay Heat Removal from the Depressurized Reactor Outer Surface Cooler Is Working .... 456
10.4.5Discussion of Parameters Relevant for the Concept ofSelf-actingDecayHeatRemoval ...................... 460
10.4.6Self-acting Decay Heat Removal from the Reactor, Total Loss of Active Cooling of the Core, and Failure of the Surface Cooler............................................ 464
10.4.7Change of Core Temperature in Accidents and Change ofStateofReactivity ................................. 466
10.4.8Self-acting Decay Heat Removal in Extreme Accidents ReactorCoveredbyRubble........................... 468
10.5 ReactivityAccidents ......................................... 470
10.5.1Overview .......................................... 470
10.5.2Extreme Reactivity Accidents in Modular HTR .... ..... .... 470
10.5.3Water Ingress into the Core, Change of the Moderation Ratio ............................................. 474
10.5.4General Considerations on Reactivity Accidents ... ..... .... 475
ContentsY
10.6 WaterIngressintothePrimarySystem ........................... 477
10.6.1Overview on General Aspects and Consequences oftheAccident ..................................... 477
10.6.2Estimation of Water Ingressing into the Primary Circuit .. .... 478
10.6.3Thermodynamic Equilibria for the SteamGraphite Reactions .......................................... 479
10.6.4Reaction Speed of Graphite Corrosion by Steam ... ..... .... 481
10.6.5Some Technical Aspects of Water Ingress into a Hot PebbleBed......................................... 484
10.6.6RiseinPressureinPrimaryCircuit ...................... 487
10.6.7Gas Formation During Water Ingress into the Reactor.... .... 489
10.6.8Reactivity Effects caused by Water Ingress ... .... ..... .... 493
10.6.9ValuationofWaterIngressAccidents .................... 494
10.7 IngressofAirintothePrimaryCircuit ........................... 497
10.7.1Overview on Aspects of Air Ingress Accidents .... ..... .... 497
10.7.2Thermodynamic Equilibria of Reactions . .... .... ..... .... 498
10.7.3Reaction Velocities of Air with Graphite . .... .... ..... .... 499
10.7.4ConsequencesofAirIngressAccidents ................... 501
10.7.5Principle Considerations on the Mass Flow of Air IngressingintothePrimarySystemofHTR ............... 501
10.7.6Conclusions on Results of Analysis of Air Ingress Accidents .......................................... 506
10.7.7Further Options to Reduce the Consequences of Air Ingress ............................................ 506
10.8 Accidents on the Secondary Side of the Steam Cycle ... .... ..... .... 507
10.8.1Overview .......................................... 507
10.8.2RuptureoftheMainSteamPipe ........................ 508
10.8.3Failure of the Turbine-Generator System; Load Rejection ofTurbine ......................................... 509
10.9 ImpactsfromtheOutsideontheReactorPlant ..................... 512
10.9.1OverviewonImpacts ................................. 512
10.9.2AirplaneCrash ...................................... 514
10.9.3Earthquakes ........................................ 519
10.10 ReleaseofFissionProductsDuringAccidents ..................... 521
10.10.1Overview on Source Terms of Radioactivity .. .... ..... .... 521
10.10.2Fission Product Release During Operation of the Plant Over the Entitle Lifetime First Source Term . .... ..... .... 525
10.10.3Fission Product Release During Core Heatup Accidents SecondSourceTerm ................................ 531
10.10.4Transport of the Released Radioactivity from the Core totheEnvironment .................................. 532
10.10.5Radioactive Source TermsConclusions .................. 535
10.11 Radiological Consequences of Accidents and Risk . .... .... ..... .... 536
10.11.1OverviewonConceptsofRisks......................... 536
10.11.2ImportanceofLandContaminations ..................... 540
10.11.3Dose Rates Caused by Accidents of Modular HTR . ..... .... 542
10.11.4General Remark on Risks Caused by Nuclear Technologies ....................................... 546 References ....................................................... 549
11 Fuel Cycles and Waste Management ................................. 555
11.1 OverviewonFuelCycles ..................................... 555
11.2 FabricationofFuelElements................................... 562
11.3 IntermediateStorageofSpentFuelElements ...................... 568
YL Contents
11.4AccidentsinIntermediateStorageSystemsforSpentFuel ElementsandDuringTransport................................. 580
11.5FinalStorageofSpentFuelElements............................ 584
11.6 NonproliferationandSafeguardAspects.......................... 596
References....................................................... 605
12 Economic Aspects of Power Plants and Questions of Optimization ......... 607
12.1OverviewonEconomicalConsiderations......................... 607
12.2EquationforCalculationoftheCostofElectricity Generation................................................. 610
12.3InvestmentCostsandCapitalFactors............................ 612
12.4Ef.ciencyandFull-PowerHoursofOperation..................... 614
12.5CostofFuelSupplyandWasteManagement...................... 615
12.6TotalCostsofElectricityGeneration ............................ 620
12.7ComparisonofProductionCostsofDifferentPower PlantsandSensitivityofCosts................................. 623
12.8EscalationofCostsandMethodsofEvaluation .................... 626
12.9ExternalCostsofElectricityProduction.......................... 627
12.10 InvestmentCostsofNewlyDevelopedConcepts ofNuclearPowerPlants...................................... 630 References....................................................... 634
|
|
購物車/收銀台(0) | 在線留言板
| 付款方式
| 聯絡我們
| 運費計算
| 幫助中心 |
加入書簽
HOME
新書上架
