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Factors Considered in Material Selection

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Ability to Withstand Stress, Environment and Temperature Over Life Time ... Nimonic PE16. Inconel 718. Inconel 617. Alloy 800H. To Avoid SCC in. Steam-Water System ... – PowerPoint PPT presentation

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Title: Factors Considered in Material Selection


1
  • Factors Considered in Material Selection
  • (Nuclear Reactors)
  • Physical Properties
  • Density
  • Melting Point
  • Coefficient of Linear Expansion
  • Thermal Conductivity
  • Mechanical Properties
  • Yield Strength
  • Tensile Strength
  • Elongation at Fracture (Ductility)
  • Creep Strength
  • Fatigue Life
  • Creep-Fatigue Interaction
  • Impact Strength and Fracture Toughness
  • Neutronic Characteristics

2
  • Factors Considered in Material Selection
  • (Nuclear Reactors)
  • Ability to Withstand Stress, Environment and
    Temperature Over Life Time
  • Previous Experience Under Similar Conditions, if
    any
  • Availability
  • Affordability
  • Ease of Fabrication
  • Susceptibility to Chemical Attack and Corrosion
  • Guidelines for Design in Codes
  • Potential for Activation Under Neutron
    Bombardment

3
  • Steels Commonly Used in
  • Nuclear Plants
  • Carbon Steels ( C 0.10 to 0.20 )
  • (Pressure Vessels of PWR, BWR, Pipings of BWR
    -Primary Pressure Boundary Piping)
  • A501, A508, A533, SA333
  • Low Alloy (Bainitic) Steels
  • (Turbine Rotors, Discs)
  • 1Cr-1Mo-0.25V
  • 2.25Cr-1Mo (Grade 22)
  • Ni-Cr-MoV (A469, Class 8)
  • Ni-Cr-MoV (A470, Class 8)
  • Ni-Cr-MoV (A471, Class 8)
  • Ferritic(Martensitic) Stainless Steel
  • (turbine blades, end fittings in PHWR)
  • AISI 403 (S40300)
  • AISI 410 (S41000)

4
  • Steels Commonly Used in
  • Nuclear Plants
  • Austenitic Stainless Steels
  • (Good Strength Ductility Resistance to
    Corrosion at High Temperatures)
  • AISI 304
  • AISI 316
  • AISI 304 L (Low Carbon, lt0.03 )
  • AISI 316 L (Low Carbon, lt0.03 )
  • AISI 304 LN (Low Carbon Nitrogen)
  • AISI 316 LN (Low Carbon Nitrogen)
  • AISI 321 (Ti stabilised)
  • AISI 347 (Nb stabilised)
  • AISI 308 (Welding electrodes)
  • Primary Coolant Pipeings of BWR 304 SS
  • 304 SS Susceptible for IGSCC
  • If IGSCC is to be Avoided 304 L, 316 L, 347
    Inconel 600 can be used

5
  • Superalloys Commonly Used in
  • Nuclear Plants
  • Superalloys
  • Inconel Alloys (Ni-Cr Series)
  • Inconel 600
  • Inconel 625
  • Inconel 690
  • Inconel 800
  • Nimonic PE16
  • Inconel 718
  • Inconel 617
  • Alloy 800H

To Avoid SCC in Steam-Water System BWR, PWR,
PHWR
FBRs (Tie Rods,Cladding Core Cover Plate
HTGR (Heat Exchanger Tubes)
6
  • Materials Commonly Used in
  • Nuclear Plants
  • Steam Generator Tubing
  • LWR Inconel 600
  • PWR Inconel 600
  • PHWR Inconel 800
  • HTGR Alloy 800 H - Creep Resistance
  • PFBR Mod. 9Cr-1Mo -Creep, SCC
  • FBTR 2 1/4Cr-1Mo - Low Temp. lt427 oC
  • Steam Condenser
  • Admiralty Brass - Fresh water
  • Aluminum - Bronze
  • Aluminum - Brass (SB 261)
  • Cupro - Nickel (SB111, 251)

SCC Resistance
Sea Water Cooled Condensers (Higher Corrosion
Resistance)
Higher Life upto 40 yrs
7
ASTM Standards for Mechanical Properties
Evaluation
8
  • FUEL STRUCTURAL MATERIALS
  • Selection Criteria
  • Low neutron absorption cross section
  • Low cost
  • Adequate tensile strength
  • Adequate creep strength
  • Adequate ductility after irradiation
  • Corrosion resistance
  • Materials

9
  • CONTROL MATERIALS
  • Selection Criteria
  • Neutron absorption cross section
  • Adequate mechanical strength
  • Corrosion resistance
  • Chemical and dimensional stability
  • (under prevailing temperature and
    irradiation)
  • Relatively low mass to allow rapid movement
  • Fabricability
  • Availability and reasonable cost
  • Materials
  • Boron, Cadmium, Gadolinium, Hafnium, Europium

10
  • MODERATOR MATERIALS
  • To slow down and moderate fast neutrons from
    fission
  • Materials with light nuclei are most effective

Moderating ratio macroscopic scattering cross
section / absorption cross section
  • REFLECTOR MATERIAL
  • To cut down the neutron leakage losses from core
  • Desired properties same as moderators

Water Heavy Water Beryllium Graphite
Thermal Reflectors
11
  • SHIELDING MATERIAL
  • To protect personnel and equipment from the
    damaging effects of radiation
  • Good moderating capability
  • Reasonable absorption cross section
  • Cost and space availability
  • Neutron, a,b and g shielding
  • Both light and heavy nuclei are preferred
  • WATER
  • PARAFFIN
  • POLYETHYLENE
  • Pb, Fe, W
  • Boral (B4C in Al matrix)
  • Concrete

12
Major Power Reactors and their Ceramic Components
a pellets b sphere-pac c coated particles
13
  • SCHEME OF PRESENTATION
  • Fundamental Aspects of Mechanical Testing and
    Various Mechanical Properties
  • ASTM Standards for Various Mechanical Tests
  • Factors Considered in Materials Selection
    (Nuclear Reactors)
  • Types of Materials in Nuclear Reactors
  • Cladding Materials in Thermal Reactors (Zirconium
    Alloys)
  • Cladding Materials in FBRs
  • Different NDT Techniques Principles
  • Application of NDT Techniques in Nuclear Industry
  • Different Types of Corrosion
  • Corrosion Protection Methods
  • Corrosion in Nuclear Plants
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