Nuclear Physicskgut.ac.ir/uploads/سرفصل_های_راکتور.pdf · 2018-05-20 · 45 1-Nuclear...

74
29 Nuclear Physics . Shell "Decay" "Interaction"

Transcript of Nuclear Physicskgut.ac.ir/uploads/سرفصل_های_راکتور.pdf · 2018-05-20 · 45 1-Nuclear...

  • 29

    Nuclear Physics

    .

    Shell

    "Decay"

    "Interaction"

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    Mean Free Path

    "Capture"

    "Transport"

    2. HILL, 1967.3. FOSTER, A. R. & WRIGHT, R. L. "BASIC NUCLEAR ENGINEERING". 3Rd Ed .19774. LAMARSH, J, "NUCLEAR REACTOR THEORY".ADDISON WESLEY INC., 1966.5. EVANS, R. D., "THE ATOMIC NUCLEUS".MCGRAW HILL,NEWYORK, 1955

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    Nuclear Physics Lab

    SURFACE BARRIER

    X

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    X

    1. MEASUREMENT & DETECTION OF RADIATION, N. TN. TWOULFARDIS, 1983,MCGRAW HILL.

    2. RADIATION DETECTION, W. H. TAIT, 1980, BUTTERWORTHS.3. METNODS OF EXPERIMENTAL PHYSICS, VOL. 5, DARA, RUC. PHYSICS,

    ACADEMIC PRESS, 1961.

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    Principles ofThermohydraulic

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    Flow Pattern

    Head

    NU ,GR

    ,PR ,RE

    Tube Bundle

  • 35

    LMTDF

    NTU

    1. PRINCIPLES OF UNIT OPERATION, MC CABE SMITH.2. FLUID MECHANICS, WHITE, 1986, MCGRAW HILL3. FLUID MECHANICS, V. L. STREETER, 1979, MC GRAW HILL.4. HEAT TRANSFER, J. P. HOLMAN, MCGRAW HILL, 1982, 6th Ed.5. PRINCIPLES OF HHEAT TRANSFER, KREITH, INTEXT PUB. CO, 1973.6. BASIC HEAT TRANSRER, N, OZISIK, MC GROW HILL, 1980.

  • 36

    HealthPhysics

    (KERMA)

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    1- Intro, Health phy s. Cember 1983.2- Health phys, for scientists. Eng. J. cob Shapiro.3- Atom Radiation & Radiation protection. Turner 1986.4- Radiation Dosimeterattics.

  • 38

    ReactorPhysics 1

    Fick

    Fick

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    1. Lamarsh J, Introduction to nuclear reactor engineering.2. Lamarsh J, Nuclear reactor teory.

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    Reactor Lab.

    Rod Calibrator

    Flux Distribution

    Reactor Power Calibration

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    1- W.J. Strum, "Reactor Laboratory Experiments", ANL- 6410, 1961

    Nuclear HeatTransfer

    core

    Poisson

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    Lumped

    Finite difference

    Chimney

    1- EL Wakile, E., "Nuclear Heat Transfer", Int'l, Text book Co, 1971

  • 43

    Nuclear Powerplants

    Technology

    PWRBWRHWR

    Reheat cycleWorking

    Fluid

  • 44

    Broun FerryBWR- 6

    HWR

    PressurizedPressure tube H.W.R

    Pichring

    chinch river

    DBALOCA

    TMI

    LWR

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    1- Nuclear Energy conversion M. EL-WAR, 1971.2- BIR-6 General Description of a Boiling water reactor 10 the printing, Jan 1973.3- Basic Nuclear ENG. Foster & Wright, 19774- Systems summary of awwestinghous PWR Nuclear power plant.5- CANDU, Nuclear power station, at ic Energy o of Canada limited, OCT, 1977.6- PHWR- 300, Pressurized heavy water reactor Nuclear power plant, KWU, March1984.7- Nuclear Energy Technology: Theory & practice of commercial Nuclear power, Ronald AllenKief, 1981.

  • 46

    ReactorPhysics 2

  • 47

    1- DUDERSTADT, J, T., HAMILTON, L.J. NUCLEAR REACTOR ANALYSIS, JOHNWILEY & SONS2- LAMARASH J, NUCLEAR REACTOR THEORY WESLEY INC, 1966.

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    Two-PhaseFlow

    BWR

    Void FractionSlipHoldup

    Tow phase separated flow

    slug & BubbleBank off

    Wallis

    Annular

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    Nucleation

    Turbulent

    Burn out

    Constitutive

    DiffusionZuber & Findlay

    Critical & Oscillatory Two phase flow

    (vois

    void faction

    Findly Zuber

  • 50

    S.S.Subchannel Analysis

    Trans

    Blow down

    DNBDNB

    Quenchingpost dray

    outsteam BindingBallooning

    Cooling Channel Block age

    1- Two phase flow & heat transfer with apply application to unclear reactor design problems byJ. Giroux Hemisphere publishing co, 1973.2- Nuclear heat Transfer H, M, EL-W IRJ, and Text book Co. 1971.3- Tow phase flow & heat transfer in the power & process industry, A.E. Bergles, J.G. collier,J.M.Delhay, C.F. Hewitt, F. Mayinger Hemisphere pub. Crop, 1981.

  • 51

    AdvancedNumerical

    Computations

    Wielandt

  • 52

    Truncation

    WRMVariational

    F.E

    1- SHRCHIRO & NAKAMURA, "COMPUTATIONAL IN ENGINEERING AND SCIENCEWITH APPLICATIONS TO FLUID DYNAMICS AND NUCLEAR SYSTEMS", JOHNWILEY & SONS, 19772- CLARIC Jr.M., & HANSEN K.F., "NUMERICAL METHODS of REACTOR ANALYSIS",A.P., 1964.

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    Shielding

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    1- Cember, H., Introduction to Health Physics2- D Ed., Pergamum Press, 1983.

    FastBreedersReactor

  • 55

    Doppler

    1- Walter, A., Fast Breader Reactor, 1980, M. G. Hill

  • 56

    NuclearReactorSafety

    Fault treeAccident tree

  • 57

    localLWR

    1- Leuise, E.E., "nuclear power reactor safety", JOHN WILEY, 19772- MC Cromick, N.J., "Reliability& Risk Analysis", Academic Press, 1981

  • 58

    AdvancedReactorPhysics

    SOR

    Discrete OrdinateSN

    SN

  • 59

    Variational

    Coupling Constantspartial

    current

    1- Bell and Glasstone, Nuclear reactor theory.

  • 60

    NuclearMaterials 1

    (Coolants)(Moderators)

    (Reflectors)(Control materials)

    (Structural materials)( Blanket materials)

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    ( Shielding Materials)

    (swelling)(fatigue)(Thermal &

    Displacement Spikes)(Radiation Hardening)

    (Reflectors)(

    BC 4

    Ag-Cd-In

    Ag Ir Hf Ag Hf

    (Burnable absorber)Eu2O3,Er2O3,Gd2O3

    1-Olander, "Fundamental Aspects of Nuclear Reactor Material .2-Benjamin M.Ma, Nuclear Reactor Materials and Application, Oct, 1982,Springer.3-Characterization and Testing of Material for Nuclear Reactors, IAEA, Tech Doc-1545,2005.

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    NuclearMaterials 2

    Zr-2Zr-4

    GridsSpacers

    Guide tube

    Nozzles

    Structural Materials

    Pressure Vessel

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    ( Al-Cu-Ni , Ti)

    (Pressurizer)

    Blanket Materials

    Th-232U-238

    Shielding Materials

    1-Olander, "Fundamental Aspects of Nuclear Reactor Material ational, Technical Information.2-Benjamin M.Ma, Nuclear Reactor Materials and Application, Oct, 1982,Springer.3-Characterization and Testing of Material for Nuclear Reactors, IAEA, Tech Doc-1545,2005.

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    Fuel Cycle 1

    Burn- up

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    U-ALXAL-U3O8U-SiU-Mo

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    Fuel Cycle 2

    CascadeSimple cascade

    Recycle cascadeIdeal Cascadeclose-

    separation cascade

    Gaseous DiffusionGaseous Centrifuge

  • 67

    Purex

    1- Benediet, Pigford &level, Nuclear chemical Engineering, McGraw Hill, 198

  • 68

    FusionReactor 1

    Drift

    Tokamak

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    1- Weston M.S.Ir., An Introduction to the Physics & Technology of Magnetic continementfusion, Iohn Wiley, 1984.2- Chen, F., Introduction to Plasma Physics, Plenum Press 1974.

  • 70

    FusionReactor 2

    MHD

    Bremsstrahlung

    Tokamak

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    NC

    MHD

    MHD

    Theta- pinch

    1- Kammash, Terry, Fusion Reactor Physics Ann arbor Science, 19762- Chen, F.F., Introduction to Plasma Physics, Plenum press, 1974.3- Snonet, J.L. the plasma attar, Academic press, 1971

  • 72

    AdvancedTopics inMaterials

  • 73

    AdvancedTopics inSafety &Nuclear

    Protection

  • 74

    AdvancedTopics inReactor

    Engineering

  • 75

    AdvancedTopics in

    FusionReactors

  • 76

    FuelManagement

  • 77

    NuclearEnergy

    Economy

  • 78

    load

  • 79

    2- Expansion Planning for Electric Generation Systems IAEA, Tech-3- Least Cost Electric Utility Planning Stoll, 19894- Eid Invitation Specification for N.P.P. IAEA. Tech. Rep. No 175, 19885- Economic Evaluation of Bids for N.P.P. IAEA, Tech. Rep. No 169, 19876- Promotion and Financing of Nuclear power program in dev. lopping countries IaEa, 1987.7- Nuclear power project management, IAEA, Tech, rep. No. 179, 1988.

  • 80

    Applicationof Monte-

    CarloMethod inNuclear

    Calculation

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    1- Monte Carlo Methods, volume 1: Basics By: M.H.kalos & P.A. WhitlockJohn Wiley & SonsInc. (1986)2- Particle- Transport simulation with the MonteCarlo method , L.L. carter & E.D. cash well.

    2- Computing methods in Reactor physics (chap 5) By: M.H. kalos et al. Gordon & Breach(1968)

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    ReactorDynamics

    In hour

    ramp

    hypergemetry

    Reactivity feedback and power Excursion

    Nordheim- Fucks

    Routh Criterion

    Nyquist CriterionRoot- Lucas

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    1- HETRICK, DAVID L., "DYNAMIC OF NUCLEAR REACTORS", THE UN.OF CHICAGOPRESS, 19712- ASH, M. "NUCLEAR REACTOR KINETICS", MCGRAW- HILL, NEWYORK, 1965.3- WEAVER, L.E.., "SYSTEM ANALYSIS OF NUCLEAR REACTOR DYNAMICS",NEWYORK, ROWMAN AND LITTLE FIELD, 1963.4- WEAVER, L.E., "REACTOR DYNAMICS AND CONRIL STATE SPACETECHNIQUES", NEWYORK, AM.ELSEVIER, 1968.

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    Post-IradiationExamination of

    Nuclear Fuels andCunstruction

    Materials

  • 85

    Examination postIrradiation

    PIE

    MTR(Material Testing Reactor)

    PIE

    PIE

    PIE

    PIE

  • 86

    1-Post Irradiation Examination and Testing, a requlatory perspective, National Post-IrradiationExamination Workshop, Maryland, 2011.2- High Temperature Gas Cooled Reactor Fuels and Materials, IAEA TECDOC 1645,2010.3-WWW.roseators.ru-BN-800,2013.4-WWW.world nuclear.org, research reactors,2013.5-Oak Ridge national Laboratory, ORNL/TM-7607, Fabrication of High-Uranium loaded U3O8-Al development fuel plates, Dec,1980.6-Current Status of U3Si2 Fuel Elements Fabrication in Brazil, M. Durazzo, et al,Brazel, 1996.activities for Hanaro Fuel Production at Kaeri,2004.7-Multipurpos Research Reactor (RMB),CNEN,2013.8-

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    Waste Managementin All Stages of Fuel

    Cycle

  • 88

    UO2UF6UF6

    UO2

    UO2

    UO2UF6

    UF6

    UF6UO2

    UO2

    1-World Nuclear Association, Radiactive Waste Management, Nov, 2013.2-Disposal Approaches for Long Lived Low and Intermediate Level Radioactive Waste, IAEA,NW-T-i-20,2009.3-Costing of Spent Nuclear Fuel Storage, IAEA, NF-T-3.5,2009.Policies and Strategies for Radioactive Waste Management, IAEA, NW-G-1.1,2009.

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    TransportTheory

  • 90

    PN

    PNp1p1

    p3

    MOMENTDECOMPOSITIONP0

    1- Bell and Glasstone, Nuclear Reactor theory

  • 91

    Introductionto Nuclear

    Codes

    deterministicprobabilistic

    WIMS

    CITATION

    WIMS

  • 92

    COBRA

    MCNP

  • 93

    Chemistry ofFuel CycleOperations

    Solvent Extraction

  • 94

    Post-IradiationExamination of

    Nuclear Fuels andCunstruction

    Materials

    Examination postIrradiation

    PIE

    MTR(Material Testing Reactor)

  • 95

    PIE

    PIE

    PIE

    PIE

    1-Post Irradiation Examination and Testing, a requlatory perspective, National Post-IrradiationExamination Workshop, Maryland, 2011.2- High Temperature Gas Cooled Reactor Fuels and Materials, IAEA TECDOC 1645,2010.3-WWW.roseators.ru-BN-800,2013.4-WWW.world nuclear.org, research reactors,2013.5-Oak Ridge national Laboratory, ORNL/TM-7607, Fabrication of High-Uranium loaded U3O8-Al development fuel plates, Dec,1980.6-Current Status of U3Si2 Fuel Elements Fabrication in Brazil, M. Durazzo, et al,Brazel, 1996.activities for Hanaro Fuel Production at Kaeri,2004.7-Multipurpos Research Reactor (RMB),CNEN,2013.8-

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    NuclearMaterials 1

    (Coolants)

    (Moderators)

    (Reflectors)

    (Control materials)

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    (Structural materials)

    ( Blanket materials)

    ( Shielding Materials)

    (swelling)

    (fatigue)

    (Thermal & Displacement Spikes)

    (Radiation Hardening)

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    (Reflectors)(

    BC 4

    Ag-Cd-In

    Ag Ir Hf Ag Hf

    (Burnable absorber)Eu2O3,Er2O3,Gd2O3

    1-Olander, "Fundamental Aspects of Nuclear Reactor Material ormation.2-Benjamin M.Ma, Nuclear Reactor Materials and Application, Oct, 1982,Springer.3-Characterization and Testing of Material for Nuclear Reactors, IAEA, Tech Doc-1545,2005.

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    Nuclear FuelCycle 1

    Burn- up

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    U-ALXAL-U3O8U-SiU-Mo

    1- Benediet, Pigford &level, Nuclear chemical Engineering, McGraw Hill, 198

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    Quality Controland Quality

    Assurance inNuclear Fuel

    Cycle

    QA/QC

    QC( Quality Control)

    QC

    QCUO2

    QCUF 6

    QCUF 6

    QCUO2

    QC

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    QC

    QC

    QC

    Quality Management system

    -Nuclear Safety RegulationIAEA50-C/S6Q-ISO -9000

    Measurement Assurance system

    Standardization system

    Clearance system

    :

    1-Advanced Methods of Process/Quality Control in Nuclear Reactor Fuel Manufacture, IAEA-TECDOC-1166,18-22 Oct,1999.2-Quality Assurance Requirements For Nuclear Facility Applications, Presented By RobertG. Burns, PE 32nd national energy and environmental division conference in San Antonio,Texas,2005.3-Characterisation and Quality Control of Nuclear Fuels, C Ganguly R N Jayaraj,2004.4-Quality Assurance in Nuclear Fuel Research at the Laboratory of High and Medium levelActivity at SCK.CE L.Sannen,A.Gys&M. Verwerft,1999.