Title: ASTM cylindrical tension test specimen Extra Slides Follow
1ASTM cylindrical tension test specimen
2Types of tensile fractures
3Engineering Stress-strain curve
4Determination of Yield strength by off-set method
5Typical stress-strain curves
6Yield Point Behaviour in Low-Carbon Steel
7Typical Creep-curve
8Andrades analysis of the competing
processes Which determine the creep curve
9Effect of stress on creep curves at constant
temperature
10Schematic stress-Rupture Data
11Fatigue test curve for materials having
an endurance limit
12Methods of Plotting Fatigue data when the
mean Stress is not zero
13Alternative method of plotting the Goodman diagram
14Response of metals to cyclic strain cycles
15Construction of cyclic stress-strain curve
16Parameters associated with the stress-strain
hysteresis loop in LCF testing
17Fatigue strain-life curve obtained by
superposition of elastic and plastic strain
equations (schematic)
18Fatigue failure
19Schematic representation of fatigue crack
growth Behaviour in a non-aggressive environment
20Sketch showing method of loading in Charpy
and Izod impact tests
21The method by which Izod Impact values
are measured
22Impact energy absorbed at various temperatures
23Transition temperature curve for two
steels Showing fallacy of depending on room
Temperature results
24Various criteria of transition temperature
obtained from Charpy test
25Effect of section thickness on transition temperat
ure curves
26PFBR heat transport flow sheet.
27PFBR reactor assembly showing major components
28Principal Selection Criteria for LMFBR Core
Structural Materials
29Schematic of fuel subassembly showing the cut out
of fuel pins, bulging and bowing.
30Variation with dose of the maximum diametral
deformation of fuel pins
31Materials selected for cladding in major FBRs
32Principal Selection Criteria for FBR Structural
Materials
33Comparison of creep rupture strengths of 316 and
316L(N) SS from various countries
34Principal Selection Criteria for LMFBR Steam
Generator Material
35Comparison of 105 h creep rupture strengths of
several materials
36 Creep-rupture strength of eleven types of
ferritic heat resistant steels
37Materials selected in FBRs for major components
for pool-type reactor, there is no hot leg
piping
38Comparison 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)
39Materials Selected for Steam Generator in Fast
Breeder Reactors
40Materials 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
42DESIRABLE MECHANICAL PROPERTIES OF ZIRCONICUM
ALLOYS for PRESSURE TUBES
43SYNERGISTIC 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
44Important steps in fabrication flow sheets of
Zirconium components for PHWR and BWR
45Long 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
47Irradiation 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
48Change in room temperature tensile properties of
mild steel produced by neutron irradiation
49Stress-strain curves for polycrystalline
copper tested at 20 oC after irradiation to the
does indicated
50Accelerated 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
52Schematic illustration of the Ludwig-Davidenkov Cr
iterion for NDTT and its shift with irradiation
53Effects of residual elements on sensitivity to
irradiation embrittlement of steel
S Strong Effect M Mild Effect
54Extra Slides Follow
55Effects of fast reactor irradiation on the
tensile properties of solution annealed 316
stainless steel
56Irradiation creep results from pressurized tube
of 20 cold worked 316 stainless steel
57Linear stress dependence of irradiation Creep in
316 stainless steel at 520 oC and a fluence of
3 x 1022 n.cm-2
58Defects Produced by Irradiation
59Summary of results of dislocation dynamics In
irradiated materials
60Crack-deformation modes
61Relation between fracture toughness and
allowable stress and crack size
62Effect of specimen thickness on stress and mode
of fracture
63Common specimens for KIc testing
64Load 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
66KQ Fracture toughness PQ Maximum recorded
load B Specimen thickness W Specimen
Width a Crack length
67Drop-weight test (DWT)
68Chemical composition specified for 316L(N),
316FR and 316LN used/proposed in EFR, DFBR and
Superphenix, respectively.
69Texture developed due to pilgering, sheet
rolling and wire drawing (cold working) operations
70Fracture appearance vs. temperature for
explosion crack starter test