The experimental investigations of two dissimilar metal weld (DMW) joints between SA508Gr.3Cl.1 ferritic steel and SS304LN austenitic stainless steel using Inconel 82/182 (ERNiCr-3/ENiCrFe-3) and Inconel 52/152 (ERNiCrFe-7/ENiCrFe-7) filler metals have been conducted in the present work. The integrity assessment of DMW joints and the mechanical properties variations has made pertaining to ASME Section-III and Section-IX. Mechanical tests comprising bend test, transverse tensile test (TTT), tensile test, Charpy impact test, microhardness measurement have been carried out along with microstructural evolution using the standard test specimens according to respective ASTM standards. Bend tests have shown that interfaces of the SA508–Inconel, Inconel–Inconel, and Inconel–SS304LN are free from any lack of fusion or cracks. TTTs have shown that failures of the specimens are from the SS304LN indicating integrity of the weld joint. Tensile tests confirm that tensile strength of the different regions agreed the required strength as per ASME Section-II. The weld strength mismatch and plastic instability strength (PIS) are found to be important factors during integrity assessment of joints. Based on the comparative investigations, owing to better mechanical properties, Inconel 82/182 filler metals could be an optimum choice over Inconel 52/152 filler metals for present DMW joints required in pressure vessel system of nuclear plants.
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February 2016
Research-Article
Mechanical Properties Variations and Comparative Analysis of Dissimilar Metal Pipe Welds in Pressure Vessel System of Nuclear Plants
Dinesh W. Rathod,
Dinesh W. Rathod
Department of Mechanical Engineering,
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: dineshvrathod@gmail.com
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: dineshvrathod@gmail.com
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Sunil Pandey,
Sunil Pandey
Department of Mechanical Engineering,
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: spandey@mech.iitd.ernet.in
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: spandey@mech.iitd.ernet.in
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P. K. Singh,
P. K. Singh
Reactor Safety Division,
Bhabha Atomic Research Centre,
Hall 7, Trombay,
Mumbai 400085, India
e-mail: pksingh@barc.gov.in
Bhabha Atomic Research Centre,
Hall 7, Trombay,
Mumbai 400085, India
e-mail: pksingh@barc.gov.in
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Rajesh Prasad
Rajesh Prasad
Department of Applied Mechanics,
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: rajesh@am.iitd.ac.in
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: rajesh@am.iitd.ac.in
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Dinesh W. Rathod
Department of Mechanical Engineering,
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: dineshvrathod@gmail.com
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: dineshvrathod@gmail.com
Sunil Pandey
Department of Mechanical Engineering,
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: spandey@mech.iitd.ernet.in
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: spandey@mech.iitd.ernet.in
P. K. Singh
Reactor Safety Division,
Bhabha Atomic Research Centre,
Hall 7, Trombay,
Mumbai 400085, India
e-mail: pksingh@barc.gov.in
Bhabha Atomic Research Centre,
Hall 7, Trombay,
Mumbai 400085, India
e-mail: pksingh@barc.gov.in
Rajesh Prasad
Department of Applied Mechanics,
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: rajesh@am.iitd.ac.in
Indian Institute of Technology Delhi,
Hauz Khas,
New Delhi 110016, India
e-mail: rajesh@am.iitd.ac.in
1Present address: Department of Mechanical Engineering, Manav Rachna International University, Sec-43, Faridabad 121001, Haryana, India.
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received April 3, 2015; final manuscript received July 1, 2015; published online September 7, 2015. Assoc. Editor: Marina Ruggles-Wrenn.
J. Pressure Vessel Technol. Feb 2016, 138(1): 011403 (9 pages)
Published Online: September 7, 2015
Article history
Received:
April 3, 2015
Revised:
July 1, 2015
Citation
Rathod, D. W., Pandey, S., Singh, P. K., and Prasad, R. (September 7, 2015). "Mechanical Properties Variations and Comparative Analysis of Dissimilar Metal Pipe Welds in Pressure Vessel System of Nuclear Plants." ASME. J. Pressure Vessel Technol. February 2016; 138(1): 011403. https://doi.org/10.1115/1.4031129
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