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29
Nuclear Physics
.
Shell
"Decay"
"Interaction"
30
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
31
Nuclear Physics Lab
SURFACE BARRIER
X
32
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.
33
Principles ofThermohydraulic
34
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)
37
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
39
1. Lamarsh J, Introduction to nuclear reactor engineering.2. Lamarsh J, Nuclear reactor teory.
40
Reactor Lab.
Rod Calibrator
Flux Distribution
Reactor Power Calibration
41
1- W.J. Strum, "Reactor Laboratory Experiments", ANL- 6410, 1961
Nuclear HeatTransfer
core
Poisson
42
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
45
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.
48
Two-PhaseFlow
BWR
Void FractionSlipHoldup
Tow phase separated flow
slug & BubbleBank off
Wallis
Annular
49
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.
53
Shielding
54
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)
61
( 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.
62
NuclearMaterials 2
Zr-2Zr-4
GridsSpacers
Guide tube
Nozzles
Structural Materials
Pressure Vessel
63
( 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.
64
Fuel Cycle 1
Burn- up
65
U-ALXAL-U3O8U-SiU-Mo
66
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
69
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
71
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
81
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)
82
ReactorDynamics
In hour
ramp
hypergemetry
Reactivity feedback and power Excursion
Nordheim- Fucks
Routh Criterion
Nyquist CriterionRoot- Lucas
83
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.
84
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-
87
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.
89
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-
96
NuclearMaterials 1
(Coolants)
(Moderators)
(Reflectors)
(Control materials)
97
(Structural materials)
( Blanket materials)
( Shielding Materials)
(swelling)
(fatigue)
(Thermal & Displacement Spikes)
(Radiation Hardening)
98
(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.
99
Nuclear FuelCycle 1
Burn- up
100
U-ALXAL-U3O8U-SiU-Mo
1- Benediet, Pigford &level, Nuclear chemical Engineering, McGraw Hill, 198
101
Quality Controland Quality
Assurance inNuclear Fuel
Cycle
QA/QC
QC( Quality Control)
QC
QCUO2
QCUF 6
QCUF 6
QCUO2
QC
102
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.