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ASTM cylindrical tension test specimen

ASTM cylindrical tension test specimen. Types of tensile fractures. Engineering Stress-strain curve. Determination of Yield strength by off-set method. Typical stress-strain curves. Yield Point Behaviour in Low-Carbon Steel;. Typical Creep-curve.

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ASTM cylindrical tension test specimen

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  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. Andrade’s 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 temperature 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

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