PSI - Issue 18

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Procedia Structural Integrity 18 (2019) 385–390 25th International Conference on Fracture and Structural Integrity Integrity and Life Assessment Procedure for a Reactor Ivica Čamagić a , Zijah Burzić b , Simon A. Sedmak c,1 , Aleksandar Sedmak d , Dragan Lazarević a 25th International Conference on Fracture and Structural Integrity Integrity and Life Assessment Procedure for a Reactor Ivica Čamagić a , Zijah Burzić b , Simon A. Sedmak c,1 , Aleksandar Sedmak d , Dragan Lazarević a 25th International Conference on Fracture and Structural Integrity Integrity and ife Assessment Procedure for a Reactor Ivica Čamagić a , Zijah Burzić b , Simon A. Sedmak c,1 , Aleksandar Sedmak d , Dragan Lazarević a 25th International Conference on Fracture and Structural Integrity Integrity and Life Assessment Procedure for a Re ctor Ivica Čamagić a , Zijah Burzić b , Simon A. Sedmak c,1 , Aleksandar Sedmak d , Dragan Lazarević a 25th International Conference on Fracture and Structural Integrity Integrity and Life Assessment Procedure for a Reactor Ivica Čamagić a , Zijah Burzić b , Simon A. Sedmak c,1 , Aleksandar Sedmak d , Dragan Lazarević a 25th International Conference on Fracture and Structural Integrity Integrity and Life Assessment Procedure for a Re ctor Ivica Čamagić a , Zijah Burzić b , Simon A. Sedmak c,1 , Aleksandar Sedmak d , Dragan Lazarević a a Faculty of Technical Sciences, 7 Kneza Miloša Street, K. Mitrovica, Serbia c Military Institute of Techniques, 1 Ratka Resanovi ć a Street, Belgrade, Serbia c Innovation Center of the Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia d Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia a Faculty of Technical Sciences, 7 Kneza Miloša Street, K. Mitrovica, Serbia c Military Institute of Techniques, 1 Ratka Resanovi ć a Street, Belgrade, Serbia c Innovation Center of the Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia d Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia a Facul y of Technical Sciences, 7 Kneza M loša Street, K. Mitrovica, Serbia c Military Institute of Techniques, 1 Ratka Resanovi ć a Street, Belgrade, Serbia c Innovation Center of the Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia d Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia a Faculty of Technical Sciences, 7 Kneza Miloša Street, K. Mitrovica, Serbia c Military Institute of Techniques, 1 Ratka Resanovi ć a Street, Belgrade, Serbia c Innovation Center of the Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia d Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia a Faculty of Technical Scienc 7 K ez Miloša Street, K. Mitrovica, S rbia c Military Institute of Techniques, 1 Ratka Resanovi ć a Street, Belgrade, Serbia c Innovation Center of the Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia d Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia a Faculty of Technical Scie c s, 7 Kneza Miloša St eet, K. Mitrovic , Serbia c Military Institute of Techniques, 1 Ratka Resanovi ć a Street, Belgrade, Serbia c Innovation Center of the Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia d Faculty of Mechanical Engineering, 16 Kraljice Marije Street, Belgrade, Serbia Abstract Integrity and life assessment of structural elements or structures subjected to variable loads is necessary in order to define the control interval and removal of damages that occurred during exploitation. Integrity and life assessment of a reactor was carried out with the previously performed welding technology qualification for new and exploited parent material sheets, made of Cr-Mo steel A-387 Gr. B, with a thickness 102 mm. Exploited parent material is the part of a reactor mantle which was in exploitation for over 40 years and is in the repair stage, i.e. its mantle is being replaced with the new material. Obtained test results and their analysis should provide a practical contribution to the assessment of exploitation conditions effects on the behaviour of parent material, welded joint components and the pressure vessel (reactor) used for exploitation at elevated temperatures, all for the purpose of integrity and life assessment of the structure, along with the revitalisation and work life extension of process equipment (reactor), made of steel used for exploitation at elevated temperatures. Abstract Integrity and life assessment of structural elements or structures subjected to variable loads is necessary in order to define the control interval and removal of damages that occurred during exploitation. Integrity and life assessment of a reactor was carried out with the previously performed welding technology qualification for new and exploited parent material sheets, made of Cr-Mo steel A-387 Gr. B, with a thickness 102 mm. Exploited parent material is the part of a reactor mantle which was in exploitation for over 40 years and is in the repair stage, i.e. its mantle is being replaced with the new material. Obtained test results and their analysis should provide a practical contribution to the assessment of exploitation conditions effects on the behaviour of parent material, welded joint components and the pressure vessel (reactor) used for exploitation at elevated temperatures, all for the purpose of integrity and life assessment of the structure, along with the revitalisation and work life extension of process equipment (reactor), made of steel used for exploitation at elevated temperatures. Abstract Integrity and life assessment of structural elements or structures subjected to variable loads is necessary in order to define the control interval and removal of damages that occurred during exploitation. Integrity and life assessment of a reactor was carried out with the previously performed welding technology qualification for new and exploited parent material sheets, made of Cr-Mo steel A-387 Gr. B, with a thickness 102 mm. Exploited parent material is the part of a reactor mantle which was in exploitation for over 40 years and is in the repair stage, i.e. its mantle is being replaced with the new aterial. Obtained test results and their analysis should provide a practical contribution to the assessment of exploitation conditions effects on the behaviour of parent material, welded joint components and the pressure vessel (reactor) used for exploitation at elevated temperatures, all for the purpose of integrity and life assessment of the structure, along with the revitalisation and work life extension of process equipment (reactor), made of steel used for exploitation at elevated temperatures. 1. Introduction The long period of exploitation of a pressure vessel-reactor (over 40 years), caused certain damages to the reactor mantle. The occurrence of these damages required a thorough examination of the reactor, as well as the repair of damaged parts. Reactor repairs included the replacing of the reactor mantle with a newly built-in material. The pressure vessel in question was made of low-alloyed Cr-Mo A-387 Gr. B according to ASTM standard with 0.8-1.15% Cr and 0.45-0.6% Mo. For the designed working parameters (p = 35 bar and t = 537 °C), the material falls into the area of tendency towards decarbonisation of surfaces in contact with hydrogen. Surface decarbonisation can result in reduced material strength. The reactor's structure is a vertical pressure vessel with a cylindrical mantle. Two deep lids were welded on the upper and lower part of the mantle, of the same quality as the mantle itself. The most important process of motor oil manufacturing takes place inside this reactor, and it involves the platforming, for the purpose of changing of the structure of hydrocarbon compounds and achieving of higher octane numbers. Welding procedure qualification for plates made of new and exploited PM was performed in accordance with standard SRPS EN ISO 15614-1, [1]. Tests not prescribed by this standard, which are necessary for remaining life and integrity assessment include working temperature tests (at 540°C), 1. Introduction The long period of exploitation of a pressure vessel-reactor (over 40 years), caused certain damages to the reactor mantle. The occurrence of these damages required a thorough examination of the reactor, as well as the repair of damaged parts. Reactor repairs included the replacing of the reactor mantle with a newly built-in material. The pressure vessel in question was made of low-alloyed Cr-Mo A-387 Gr. B according to ASTM standard with 0.8-1.15% Cr and 0.45-0.6% Mo. For the designed working parameters (p = 35 bar and t = 537 °C), the material falls into the area of tendency towards decarbonisation of surfaces in contact with hydrogen. Surface decarbonisation can result in reduced material strength. The reactor's structure is a vertical pressure vessel with a cylindrical mantle. Two deep lids were welded on the upper and lower part of the mantle, of the same quality as the mantle itself. The most important process of motor oil manufacturing takes place inside this reactor, and it involves the platforming, for the purpose of changing of the structure of hydrocarbon compounds and achieving of higher octane numbers. Welding procedure qualification for plates made of new and exploited PM was performed in accordance with standard SRPS EN ISO 15614-1, [1]. Tests not prescribed by this standard, which are necessary for remaining life and integrity assessment include working temperature tests (at 540°C), 1. Introduction The long period of exploitation of a pressure vessel-reactor (over 40 years), caused certain damages to the reactor mantle. The occurrence of these damages required a thorough examination of the reactor, as well as the repair of damaged parts. Reactor repairs included the replacing of the reactor mantle with a newly built-in material. The pressure vessel in question was made of low-alloyed Cr- o A-387 Gr. B according to ASTM standard with 0.8-1.15% Cr and 0.45-0.6% Mo. For the designed working parameters (p = 35 bar and t = 537 °C), the material falls into the area of tendency towards decarbonisation of surfaces in contact with hydrogen. Surface decarbonisation can result in reduced material strength. The reactor's structure is a vertical pressure vessel with a cylindrical mantle. Two deep lids were welded on the upper and lower part of the mantle, of the same quality as the mantle itself. The most important process of motor oil manufacturing takes place inside this reactor, and it involves the platforming, for the purpose of changing of the structure of hydrocarbon compounds and achieving of higher octane numbers. elding procedure qualification for plates made of new and exploited PM was performed in accordance with standard SRPS EN ISO 15614-1, [1]. Tests not prescribed by this standard, which are necessary for remaining life and integrity assessment include working temperature tests (at 540°C), Keywords: reactor; welded joint; crack; integrity; remaining life. Keywords: reactor; welded joint; crack; integrity; remaining life. Keywords: reactor; welded joint; crack; integrity; remaining life. © 2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. Keywords: reactor; welded joint; crack; integrity; remaining life. © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of th Gruppo Italiano Frattura (IGF) ExCo. Abstract I t grity and life assessment of structural elements or structures subjected to variable loads is necessary in order to define the control interval and removal of damages t at ccurred during exploitatio . Integrity and life assessment of a reactor was carried out with the previously performed welding technology qualification for new and exploited p rent material sheets, made of Cr-Mo steel A-387 Gr. B, with a thickness 102 mm. Exploited parent m terial is the part of a r actor mantle which was in exploitation for over 40 years and is in the repair stage, i.e. its mantle is being repl ced with the ew material. O tained test results and their analysis should provide a practical contribution to the assessment of exploitation conditions effects on the behaviour of parent material, welded joint components and the pressure vessel (reactor) used f r exploitation at elevated temperatures, all for the purpose of integrity and life assessment of the structure, along with the revitalisation and work life extension of process equipment (reactor), made of steel used for exploitation at elevated temperatures. © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. 1. Introduction Th long period of exploitation of a pressure vessel-reactor (over 40 years), c used certain damages to the re ctor mantle. The occurrence of these damages required a thorough examination of the reac or, as well as t repair of damaged parts. Reactor repairs included the replacing of the reactor mantle with a newly built-in material. The p essure vessel in questi n was made of l w-alloyed Cr-Mo A-387 Gr. B according to ASTM standard with 0.8-1.15% Cr and 0.45-0.6% Mo. F r the designed working par meters (p = 35 bar and t = 537 °C), the material falls i to the area of tendency towards d carbonisation of surfaces in contact with hydrogen. Surface decarbonisation can result in r duced material strength. The reactor's structure is a vertical pressure vessel with a cylindrical mantle. Two deep lids were welded n the pper and lower p rt of the mantl , of the same quality as the mantle itself. The most important process of motor oil manufa turing takes place inside this reactor, and it involves the platforming, for the purpose of changing o the structure of hydrocarbon compounds and achi ving of higher octan numbers. Welding procedure qualification for plates made of new and exploited PM w s performed in accordance with sta dard SRPS EN ISO 15614-1, [1]. Tests not prescribed by this standard, which are necessary for remaining life and integrity assessment include working temperature tests (at 540°C), Abst act I t grity and life assessment of tructural elements or structures subjected o variable loads is neces ary in rder to defin the control interval nd removal of da ages that ccurred during exploitation. Integri y and lif assessment of a reac or was carri d out with the previously erform d welding technology qualifi ation for new and exploited p re t material sheets, made of Cr-Mo steel A-387 Gr. B, w t a thickness 102 mm. Exploited parent m terial is the part o a r actor mantl which was in exploitation for over 40 years and is in the repair stage, i.e. its mantle is being repl ced with the new at ial. Obtained est result and th ir analysis should provide a practical contribution to the assessment of l it ti conditions effects on the behaviour of parent material, welded joint components and the pressure vessel (reactor) used f r exploitation at elevated tem eratures, all for the purpose of integrity and life assessment f the structure, along with the revitalisation and work life extension of process equipment (reactor), made of steel used for exploitation at elevated temperatures. © 2018 The Authors. Published by Elsevier B.V. P er-review under responsibility of th Gruppo Italiano Frattura (IGF) ExCo. Keywords: reactor; welded joint; crack; integrity; remaining life. 1. I troduction The long period f exploitation of a pressure vessel-reactor (over 40 years), caused certain damages to the reactor mantle. T occurr nce f these da ag s required a thorough examination of the reactor, as well as the r pair of damaged parts. Reactor repairs in luded the replacing of th reactor mantle with newly built-in material. The pressu vessel in question was made of low-alloyed Cr-Mo A-387 Gr. B according to ASTM sta dard with 0.8-1.15% Cr and 0.45-0.6% Mo. For the designed working parameters (p = 35 bar and t = 537 °C), the material falls into the area of tendency towards decarbonisation of surfaces in contact with hydrogen. Surface decarbonisation can result in reduced material strength. The reactor's structure is a vertical pressure vessel with a cylindrical mantle. Two deep lids were welded on the upper lower part of the mantle, of the same quality as the m tle itself. The most important pr cess of motor oil manufacturi g takes place inside this reactor, and it involves th platforming, for the purpose of changing of the structure of hydrocarbon compounds and achieving of higher octane numbers. Welding procedure qualification for plates made of new and exploited PM was performed in accordance with standard SRPS EN ISO 15614-1, [1]. Tests not prescribed by this standard, which are necessary for remaining life and integrity assessment include working temperature tests (at 540°C), Abstract Integrity and life assessment of structural elements or struc ures subjected to variable loads is necessary in order to define the control interval and removal of damage that occurred during exploitation. Integrity and life assessment of a r actor as carried out with the previously performed welding technology qualification for new and exploited parent mat rial she ts, made of Cr-Mo steel A-387 Gr. B, with a thickness 102 mm. Exploited parent material is the part of a reactor mantle which was in exploitation for over 40 years and is in the repair stage, i.e its mantle is being replaced with the new aterial. Obtained test results and their analysis should provide a practical contribution to the assessment of exploitation conditions effects on the behaviour of parent material, welded joint components and the pressure ve sel (reactor) used for exploitation at elevated temperatures, all for the purpose of integrity and life assessment of the st ucture, along with the revitalisation and work life extension of process equipment (reactor), made of steel used for exploitation at elevated temperatures. © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. Keywords: reactor; welded joint; crack; integrity; remaining life. 1. Introduction The long period of exploitation of a pressure vessel-reactor (over 40 years), caused certa n damages to the reactor mantle. The occurrence f these damages required a thorough examination of the re ctor, as well as the rep ir of damaged parts. Reactor repairs included the replacing of the re ctor mantle with a newly built-in material. The pressure vessel in question w s made of low-alloyed Cr-Mo A-387 Gr. B according to ASTM st dard w th 0.8-1.15% Cr and 0.45-0.6% Mo. For the designed working parameters (p = 35 bar and t = 537 °C), the material falls into the area of tendency towards decarbonisation of surfaces in contact with hydrog n. Surface decarbonisa ion can result in reduced material strength. The reactor's structur is a ver ical pressure ves el with a cyl drical mantle. Two deep lids were welded on the upper and l wer part of the mantle, of the same quality as the mantle itself. The most important process of motor oil manufacturi g takes place inside this eactor, a d it involves the platforming, for the purpose of changing of the structure of hydrocarbon compounds and achi ving of higher octane numbers. Welding procedure qualification for plates made of new and exploited PM was performed in accordance with standard SRPS EN ISO 15614-1, [1]. Tests not prescribed by this standard, which are necessary for remaining life and integrity assessment include working temperature tests (at 540°C),

2452-3216  2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. 10.1016/j.prostr.2019.08.179 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. * Corresponding author. E-mail address: simon.sedmak@yahoo.com 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. * Corresponding author. E-mail address: sim n.sedmak@yahoo.com 2452 3216 © 2018 Th Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. * Correspon ing author. E mail address: simon.sedmak@ya oo.com 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Gruppo Italiano Frattura (IGF) ExCo. * Corresponding author. E-mail address: simon.sedmak@yahoo.com * Corresponding author. E-mail address: simon.sedmak@yahoo.com * Corresponding author. E-mail address: simon.sedmak@yahoo.com