普通高等教育核工程与核技术专业规划教材：核电专业英语

图书标准信息

• 作者 阎昌琪 编
• 出版社 中国电力出版社
• 出版时间 2010-07
• 版次 1
• ISBN 9787512302495
• 定价 29.80元
• 装帧 平装
• 开本 16开
• 纸张 胶版纸
• 页数 279页
• 字数 436千字
• 正文语种 英语，简体中文

【内容简介】

　　《核电专业英语》为普通高等教育核工程与核技术专业规划教材。《核电专业英语》的内容涵盖了与核电有关的基础理论知识和专业知识，介绍了反应堆结构、核动力系统和设备，也包括了近年来核电的新发展，例如第三代和第四代反应堆的介绍。书中涉及的核电专业词汇广泛、内容丰富、知识性强。
　　为了便于读者掌握专业词汇，每课课文后对重要的关键词作了英、中文两种解释，同时还列出了重要的词汇解释、课文中的难点注释。为了加深读者对课文内容的理解，课后还附有习题和答案。
　　《核电专业英语》可作为普通高等教育本科核工程与核技术专业的英语阅读教材，也可作为核电工程技术人员的培训和自学用书，同时可作为能源动力类等相关专业人员的阅读材料。

【目录】

前言
Unit1TheBasicConceptsforNuclearPhysics
1.1AtomsandNuclei
1.2Isotopes
1.3MassDefect
1.4BindingEnergy
1.5EnergyLevels
1.6Fission
Self-test
关键字解释
词汇
课文注释
Unit2Radiation
2.1Radioactivity
2.2ExcitationandIonizationbyElectrons
2.3HeavyChargedParticleSlowingbyAtoms
2.4HeavyChargedParticleScatteringbyNuclei
2.5GammaRayInteractionswithMatter
2.6ThePropertiesofAlpha,BetaandGammaRadiation
Self-test
关键字解释
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Unit3NuclearMaterials
3.1Fuels
3.2Moderators
3.3Coolants
3.4CladdingMaterials
3.5ControlMaterials
Self-test
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Unit4TheTheoryofNuclearReactors
4.1Th6ChainReaction
4.2TheNeutronCycleinaThermalReactor
4.3ConversionandBreeding
4.4FuelCycles
Self-test
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Unit5NuclearReactorConcepts
5.1PowerReactors
5.2ConsumptionofNuclearFuels
5.3ReactorControl
5.4OtherEffectsonReactorOperation
5.5TheFastBreederReactor
5.6UraniumasanEnergyResource
Self-test
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Unit6NuclearReactorThermohydraulics
6.1MethodsofHeatTransmission
6.2ConductioninReactorFuel
6.3HeatRemovalbyCoolant
6.4BoilingHeatTransfer
Self-test
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Unit7PressurizedwaterReactor
7.1General
7.2PressurizedWaterReactorComponents
7.3IntroductiontotheNuclearSteamSupplySystem80+
Self-test
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Unit8ReactorvesselandInternals
8.1ReactorVessel
8.2ReactorVesselInternals
Self-test
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Unit9ReactorCoreandFuel
9.1Introduction
9.2Core
9.3FuelRod
9.4FuelAssembly
9.5ControlElementAssembliesandDriveMechanisms
9.6ControlElementDriveMechanisms(CEDM)
9.7NeutronSources
9.8BurnableAbsorberRodAssembly
Self-test
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Unit10TheMainComponentsinPWRCoolantSystem
10.1SteamGenerators
10.2Pressurizer
10.3ReactorCoolantPumpsandMotors
Self-test
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Unit11PressurizedWaterReactorSystemsandContainment
11.1PlantHeatBalanceandtheSteamCycle
11.2PWRPrimaryandSecondaryLoops
11.3AuxiliarysystemforPrimaryLoop
11.4Containment
Self-test
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Unit12TheSteamTurbine
12.1Introduction
12.2ClassificationofTurbines
12.3ImpulseandReactionBlading
12.4VelocityCompoundingCurtisStage
12.5TheReaction-TurbinePrinciple
12.6ReactionBlading
12.7SealingArrangement
12.8TwistedandTaperedBlades
12.9ErosionControlandMoistureRemoval
12.10OtherBladeFeatures
12.11LowPressureTurbine
12.12TurbineControl
Self-test
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Unit13MainSteam,FeedandCondensateSystems
13.1Introduction
13.2MainSteamandFeedwaterPiping
13.3MainSteamPipingSystemFlowRestrictor
13.4SafetyRequirements
13.5FeedandCondensateSystemDescription
13.6Transients
13.7Controls
Self-test
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Unit14OperationofaNuclearPowerPlant
14.1Introduction
14.2PlantSafety
14.3PlantOperations
14.4NormalMode
14.5AbnormalMode
14.6Off-Normal(Upset)Mode
14.7ControlRoomsandInstrumentation
14.8SystemParameters
Self-test
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Unit15RadiationHazardsandShielding
15.1Introduction
15.2HealthPhysics
15.3TheBiologicalEffectsofRadiationExposure
15.4TheEffectsofInhaledandIngestedRadioactivity
15.5ReactorShielding
Self-test
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Unit16NuclearSafety
16.1SafetyandHazardsinNuclearPower
16.2ReactorAccidents
16.3TheAccidentatThreeMileIsland
16.4TheAccidentatChernobyl
Self-test
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Unit17WestinghouseAPl000AdvancedPassivePlant
17.1Introduction
17.2MajorEquipmentDescription
17.3SafetyThroughSimplicity
17.4PassiveSafetySystems
17.5ProbabilisticRiskAssessment
17.6Simplification
17.7CostandConstructionSchedule
17.8Licensing
17.9AP1000Deployment
17.10Conclusions
Self-test
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Unit18EuropeanPressurizedWaterReactor(EPR)
18.1Introduction
18.2ConstructionSchedule
18.3Operation,MaintenanceandServices
18.4OpreationalFlexibility
18.5SafetySystems
18.6PrimarySystem
Self-test
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Unit19TheHeavy-Water-ModeratedReactor
19.1GeneralCharacteristicsoftheHeavyWaterReactor
19.2TheCANDUPressureTubeHeavyWaterReactor
19.3AdvancedCANDUReactor
Self-test
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Unit20GenerationIVNuclearPower
20.1Introduction
20.2TheGas-CooledFastReactor(GFR)
20.3Very-High-TemperatureReactorSystem(VHTR)
20.4SupercriticalWater-CooledReactor(SCWR)
20.5Sodium-CooledFastReactor(SFR)
20.6Lead-CooledFastReactor(LFR)
20.7MoltenSaltReactor(MSR)
20.8GenerationIVandtheHydrogenEconomy
Self-test
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附录ⅠSelf-test习题答案
附录Ⅱ词汇表
参考文献