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ASTM cylindrical tension test specimen Extra Slides Follow Extra Slides Follow KQ = Fracture toughness PQ = Maximum recorded load B = Specimen thickness W ... – PowerPoint PPT presentation

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Title: ASTM cylindrical tension test specimen Extra Slides Follow


1
ASTM cylindrical tension test specimen
2
Types of tensile fractures
3
Engineering Stress-strain curve
4
Determination of Yield strength by off-set method
5
Typical stress-strain curves
6
Yield Point Behaviour in Low-Carbon Steel
7
Typical Creep-curve
8
Andrades analysis of the competing
processes Which determine the creep curve
9
Effect of stress on creep curves at constant
temperature
10
Schematic stress-Rupture Data
11
Fatigue test curve for materials having
an endurance limit
12
Methods of Plotting Fatigue data when the
mean Stress is not zero
13
Alternative method of plotting the Goodman diagram
14
Response of metals to cyclic strain cycles
15
Construction of cyclic stress-strain curve
16
Parameters associated with the stress-strain
hysteresis loop in LCF testing
17
Fatigue strain-life curve obtained by
superposition of elastic and plastic strain
equations (schematic)
18
Fatigue failure
19
Schematic representation of fatigue crack
growth Behaviour in a non-aggressive environment
20
Sketch showing method of loading in Charpy
and Izod impact tests
21
The method by which Izod Impact values
are measured
22
Impact energy absorbed at various temperatures
23
Transition temperature curve for two
steels Showing fallacy of depending on room
Temperature results
24
Various criteria of transition temperature
obtained from Charpy test
25
Effect of section thickness on transition temperat
ure curves
26
PFBR heat transport flow sheet.
27
PFBR reactor assembly showing major components
28
Principal Selection Criteria for LMFBR Core
Structural Materials
29
Schematic of fuel subassembly showing the cut out
of fuel pins, bulging and bowing.
30
Variation with dose of the maximum diametral
deformation of fuel pins
31
Materials selected for cladding in major FBRs 
32
Principal Selection Criteria for FBR Structural
Materials
33
Comparison of creep rupture strengths of 316 and
316L(N) SS from various countries
34
Principal Selection Criteria for LMFBR Steam
Generator Material
35
Comparison of 105 h creep rupture strengths of
several materials
36
Creep-rupture strength of eleven types of
ferritic heat resistant steels
37
Materials selected in FBRs for major components
for pool-type reactor, there is no hot leg
piping
38
Comparison of PFBR specification for 304L(N) and
316L(N) SS with ASTM A240 and RCC-MR
RM-3331. (single values denote maximum
permissible, NS - not specified)
39
Materials Selected for Steam Generator in Fast
Breeder Reactors
40
Materials selected for Top Shield for various
Fast Breeder Reactors
41
ZIRCONICUM ALLOYS NUCLEAR APPLICATIONS
  • Low absorption cross section for thermal neutrons
  • Excellent corrosion resistance in water
  • Good mechanical properties
  • IMPORTANT PROPERTIES OF ZIRCONIUM
  • Allotropy (a hcp b bcc )
  • Anisotropic mechanical and thermal properties
  • Unequal thermal expansions along different
  • crystallographic directions
  • Strong crystallographic texture during
  • mechanical working
  • high reactivity with O2, C, N and high
  • solubility in a -phase
  • Special care during melting and fabrication
  • Low solubility of hydrogen in a

862 oC
42
DESIRABLE MECHANICAL PROPERTIES OF ZIRCONICUM
ALLOYS for PRESSURE TUBES
43
SYNERGISTIC INTERACTIONS LEADING TO DEGRADATION
OF MATERIAL PROPERTIES IN ZIRCONIUM ALLOYS
  • Corrosion by Coolant Water
  • Corrosion by Fission Products
  • Hydrogen Ingress
  • Irradiation Damage
  • Dimensional Change due to Creep and Growth

44
Important steps in fabrication flow sheets of
Zirconium components for PHWR and BWR
45
Long term, in reactor, oxidation and hydrogen
Pick-up behaviour of zircaloy-2 and Zr-2.5Nb
pressure tubes,
46
  • Stress reorientation of circumferential zirconium
  • hydride platelets(left hand side) at 250 MPa
    stress
  • level in the direction shown
  • (b) A hydride blister in the zirconium alloy
    pressure
  • tube section

47
Irradiation creep rate in zircaloy-2 under
biaxial loading (150 MPa and 300 oC) and a
schematic diagram to show the growth rate of
cold-worked and recrystallization (RX) zircaloy 2
48
Change in room temperature tensile properties of
mild steel produced by neutron irradiation
49
Stress-strain curves for polycrystalline
copper tested at 20 oC after irradiation to the
does indicated
50
Accelerated in-reactor creep in zircaloy-2
51
  • Impact energy vs. temperature curves for ASTM 203
  • grade D steel
  • Unirradiated
  • Irradiated to a fluence of 3.5 x 1019 n.cm-2
  • Irradiated to a fluence of 5 x 1018 n.cm-2
  • Annealed at 300 oC for 15 days after irradiation
  • to a fluence of 3.5 x 1019 n.cm-2

52
Schematic illustration of the Ludwig-Davidenkov Cr
iterion for NDTT and its shift with irradiation
53
Effects of residual elements on sensitivity to
irradiation embrittlement of steel
S Strong Effect M Mild Effect
54
Extra Slides Follow
55
Effects of fast reactor irradiation on the
tensile properties of solution annealed 316
stainless steel
56
Irradiation creep results from pressurized tube
of 20 cold worked 316 stainless steel
57
Linear stress dependence of irradiation Creep in
316 stainless steel at 520 oC and a fluence of
3 x 1022 n.cm-2
58
Defects Produced by Irradiation
59
Summary of results of dislocation dynamics In
irradiated materials
60
Crack-deformation modes
61
Relation between fracture toughness and
allowable stress and crack size
62
Effect of specimen thickness on stress and mode
of fracture
63
Common specimens for KIc testing
64
Load displacement curves (slope Ops is
exaggerated fir clarity)
65
  • J vs. Da curve for establishing Jic
  • Sketch of a specimen fracture surface showing
  • how Da is determined

66
KQ Fracture toughness PQ Maximum recorded
load B Specimen thickness W Specimen
Width a Crack length
67
Drop-weight test (DWT)
68
Chemical composition specified for 316L(N),
316FR and 316LN used/proposed in EFR, DFBR and
Superphenix, respectively.
69
Texture developed due to pilgering, sheet
rolling and wire drawing (cold working) operations
70
Fracture appearance vs. temperature for
explosion crack starter test
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