PSI - Issue 14

Structural Integrity Procedia 00 (2018) 000–000 Structural Integrity Procedia 00 (2018) 000–000 ScienceDirect ScienceDirect ScienceDirect Available o line at www.sciencedirect.com ScienceDirect Available onlin at www.scien edirect.com i i t Available online at www.sciencedirect.com ScienceDirect Structural Integrity Procedia 00 (2018) 000–000 Structural Integrity Procedia 00 (2018) 000–000 Structural Integrity Procedia 00 (2018) 000–000

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ScienceDirect Available online at www.sciencedirect.com Available o line at ww.sciencedire t.com ienceDirect Structural Integrity Procedia 00 (2016) 000 – 000 Procedia Structu al Integrity 14 (2019) 4 3–4 9 2nd International Conference on Structural Integrity and Exhibition 2018 Master Curve of 20MnMoNi55 Steel From Miniature CT Specimens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Kumar b 2nd International Conference on Structural Integrity and Exhibition 2018 st r r f Ni55 t el From Miniat r i s evil artin Jose a* , J. hattopadhyay a , . . urgaprasad a , . aveen u ar b 2nd International Conference on Structural Integrity and Exhibition 2018 Master Curve of 20MnMo i55 Steel Fro iniature CT Specimens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Kumar b 2nd International Conference on Structural Integrity and Exhibition 2018 aster Curve of 20 n oNi55 Steel From Miniature CT Specimens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Kumar b 2nd International Confere ce on Structural Integrity and Exhibition 2018 Master Curve of 20MnMoNi55 Steel From Miniature CT Specimens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Kumar b 2nd International Conference on Structural Integrity and Exhibition 2018 Master Curve of 20MnMoNi55 Steel From Miniature CT Specimens Nevil Martin Jos a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Kumar b Abstract The steels used for manufacturing nuclear reactor pressure vessel re low alloy ferritic st els. There is a ra ge f s at which thes steels exhibit transitio from ductile to br ttle fracture known s th ductile to brittl transition temperature (DBTT). In these range of temperatures, ferritic steels exhibit a scat r in th fracture toughness values having a charact ristic statistical distribution which is unique to ferritic t els. The master curve methodology aims to capture this behaviour of ferritic steels through fracture m chanics principles. To obtai master curve, fracture experiments of standar s im ns as per ASTM E-1921 must be carried out. Si ce reactor pr ssur vessel st els suffer loss in ductility due to irradiation embrittlement during its service life, mast r curve needs to be generated at periodic intervals using surveillance specimens. Us of stan ard sized fracture specimens as surveillance specimens are difficult as the space availabl in a nuclear reactor for keeping these specimens are limited. Also, the radiation dose a sociated with testing stand rd sized irradiated specimens can be dangerous for the personnel involved. Under these circ mstances, it becomes nec ssary to carry out uch tests using miniaturized pecimens. I this wo k, we will obtain the fracture toughness master urve of 20MnMoNi55 teel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT specimens having a thickness of 4 mm. 2nd International Conference on Structural Integrity and Exhibition 2018 Master Curve of 20MnMoNi55 Steel Fro Miniature Speci ens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Ku ar b a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Tr mbay, Mumbai 400085, India Abstract The steels used for manufactu n nuclear reactor pressure vessel are low alloy ferritic steels. There is a range of temperatures at which these steels exhibit transition from ductile o brittle fracture known as the ductile to brittle transition temperature (DBTT). In these range of temperatures, ferritic steels exhibit a scatter in the fracture toughness values having a characteristic statistical distribution which is unique to ferritic steels. The master curve methodology aims to capture this behaviour of ferritic steels through fracture mechanics principles. To obtain master curve, fracture experiments of standard speci ens as per ASTM E-1921 must be carried out. Since reactor pressure vessel steels suffer loss in ductility due to irradiation embrittlement during its service life, master curve needs to be generated at periodic intervals using surveillance specimens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear reactor for keeping these specimens are limited. Also, the radiation dose associated with testing standard sized irradiated specimens can be dangerous for the personn l involved. U der these circumstances, it becomes n cessary to carry out such tests using miniaturized pecimens. In this work, we will obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT sp cimens having a thickness f 4 mm. Structural Int gri y Procedia 00 (2018) 000–000 2nd International Conference on Structural Integrity and Exhibition 2018 Master Curve of 20MnMoNi55 Steel From Miniature CT Specimens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durg prasad a , N. Naveen Kumar b a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India Abstract The steels used for manufacturing nuclear reactor pressure vessel are low alloy ferritic steel . There is a r nge f s at which thes steels exhibit transition from ductile to br ttle fracture known as the ductile to brittl transition temperature (DBTT). In these range of temperatures, ferritic steels xhibit a sc t in th fracture toughness values having a characteristic statistical dis ribution which is unique to ferritic teels. The master curve methodology ai s to capture this behaviour of ferritic steels through fracture mechanics pri iples. T obtain mast r curv , fracture exper ments of standard specimens as per ASTM E-1921 must b carried out. Sinc r actor pr ssur vessel st els suffer loss in ductility due to irradiati n embrittlement uring its service life, master curve needs to be gene ated at periodic intervals using surveillance spe imens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear rea tor for k eping these specimens are limited. Als , the radiation dose associated with testing st n ard siz d irradiated sp cimens can be dangerous for the personnel involved. Under these circ mstances, it becomes nec ssary to carry out uch tests using miniatu ized pecimens. In this wo k, we will obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT specimens having a thickness of 4 mm. Structural Integrity Procedia 00 (2018) 000–000 Inter ati al nfere ce tr ct ral I te rit a i iti t r C rv f 0MnMoNi55 Steel From Miniature CT Spe i il rti J s a* , J. hattopad y y a , . . r a rasad a , N. Naveen Kumar b a Reactor Safety ivision, BARC-Tro bay, u bai 40008, India b Materials Group, BARC-Tro bay, u bai 400085, India bstract The steels used fo manufacturing nucle r r a tor pressure vessel ar low lloy ferr tic st els. There i a rang of temperatures at which these steels exhibit transition from ductile to brittle fracture kno n as the ductile to brittle transition temperature ( BTT). In these range of temperatures, ferritic steels exhibit a scatter in the fracture toughness values having a characteri tic statistical distribution which is u ique to ferritic steels. The master curve methodology aims to capture this behaviour of ferritic steels through fracture mechanics principles. To ob ain mast r curve, fractur xperime ts of standard s eci e s as per ASTM E-1921 must be c rri d out. Since reactor pressure vessel steels suffer loss in ductility due to irradiation embrittlement during its service life, master curve needs to be generated at periodic intervals using surveillance speci ens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear reactor for keeping these specimens are limited. Also, the radiation dose associated with testing standard sized irradiated speci ens can be dangerous for the personnel involved. Under these circumstances, it becomes necessary to carry out such test usi g mi i turized specimens. In this work, we ill obtain the fracture toughness aster curve of 20 n o i55 steel (lo alloy ferritic st el use for aking nuclear reactor pressure vessels) fro iniature T speci ens having a thickness of 4 m . Structural Integrity Procedia 00 (2018) 000–000 2nd International Conference on Structural Integrity and Exhibition 2018 Master Curve of 20MnMoNi55 Steel ro Miniature Specimens Nevil Martin Jose a* , J.Chattopadhyay a , P. V. Durgaprasad a , N. Naveen Kumar b a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India Abstract The steels used fo manufacturing nuclear rea tor pressure vess l are low alloy ferr tic steel . There i rang of temperatures at which these steels exhibit transition from ductile to brittle fracture known as the ductile to brittle transition tempe ature (DBTT). In these range of temperatures, ferritic steels exhibit a scatter in the frac ure toughness values having a ch rac ri tic sta istical distributio which is u ique to ferritic steels. The master curve methodology aims to capture this behaviour of f rritic steels through fracture mechanics principles. To obtain mast r curve, fract r xperiments of standard speci ens as per ASTM E-1921 must be carried out. Since reactor pressure vessel steels suffer loss in ductility due to irradi tion mbrittlement during its service life, master curve needs to be generated at periodic nt rvals using surveillan e speci ens. Use of stan ard sized fracture pecimens as surveillance specimens are difficult as the space available in a nucl ar reactor for keeping these specimens are limited. Also, the radiation dose associated with testing standard sized irradiated specimens can be dangerous for the personn l involved. Under these circumstances, it becomes necessary to carry out such test using mi i turized specimens. In this work, we wi l obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic st l used for making nuclear reactor pressure v ssel ) from mi iature CT specim ns having a thickn ss of 4 mm. XV Portuguese Conference on Fracture, PCF 2016, 10-12 February 2016, Paço de Arcos, Portugal Thermo-mechanical modeling of a high pressure turbine blade of an airplane gas turbine engine P. Brandão a , V. Infante b , A.M. Deus c * a Department of Mechanical Engineering, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais, 1, 1049-001 Lisboa, Portugal b IDMEC, Department of Mechanical Engineering, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais, 1, 1049-001 Lisboa, Portugal c CeFEMA, Department of Mechanical Engineering, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais, 1, 1049-001 Lisboa, Portugal Abstract During their operation, modern aircraft engine components are subjected to increasingly demanding operating conditions, especially the high pressure turbine (HPT) blades. Such conditions cause these parts to undergo different types of time-dependent degradation, one of which is creep. A model using the finite element method (FEM) was developed, in order to be able to predict the creep behaviour of HPT blades. Flight data records (FDR) for a specific aircraft, provided by a commercial aviation company, were used to obtain thermal and mechanical data for three different flight cycles. In order to create the 3D model needed for the FEM analysis, a HPT blade scrap was scanned, and its chemical composition and material properties were obtained. The data that was gathered was fed into the FEM model and different simulations were run, first with a simplified 3D rectangular block shape, in order to better establish the model, and then with the real 3D mesh obtained from the blade scrap. The overall expected behaviour in terms of displacement was observed, in particular at the trailing edge of the blade. Therefore such a model can be useful in the goal of predicting turbine blade life, given a set of FDR data. © 2019 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. Abstract The steels used for manufacturing nuclear reactor pressure vessel are low alloy ferritic steels. There is a range of temperatures at which these steels exhibit transition from ductile to brittle fracture known as the ductile to brittle transition temperature (DBTT). In these range of temperatures, ferritic steels exhibit a scatter in the fracture toughness values having a characteristic statistical distribution which is unique to ferritic steels. The master curve methodology aims to capture this behaviour of ferritic steels through fracture mechanics principles. To obtain master curve, fracture experiments of standard specimens as per ASTM E-1921 must be carried out. Since reactor pressure vessel steels suffer loss in ductility due to irradiation embrittlement during its service life, master curve needs to be generated at periodic intervals using surveillance specimens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear reactor for keeping these spe imens are limited. Also, the radiation d se assoc ated with testing standard sized irradiated specimens can be dangerous for the personnel involved. Under these circumstances, it becomes necessary to carry out such tests using miniaturized specimens. In this work, we will obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT specimens having a thickness of 4 mm. © 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperature Abstract The steels used for anufacturing nuclear reactor pressure vessel are low alloy ferritic steels. There is a range of te peratures at which these steels exhibit transition fro ductile to brittle fracture known as the ductile to brittle transition te perature (DBTT). In these range of temperatures, ferritic steels exhibit a scatter in the fracture toughness values having a characteristic statistical distribution which is unique to ferritic steels. The master curve methodology aims to capture this behaviour of ferritic steels through fracture mechanics principles. To obtain master curve, fracture experiments of standard speci ens as per AST E-1921 must be carried out. Since reactor pressure vessel steels suffer loss in ductility due to irradiation embrittlement during ts servic life, master curve needs to be generate at periodic inter als using surveillance specimens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear reactor for keeping these speci ens are li ited. Also, the radiation dose associated with testing standard sized irradiate s ecimens can be dangerous for the personnel involved. U der these circu stances, it beco es necessary to carry out such tests using miniaturized speci ens. In this work, we will obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from iniature CT speci ens having a thickness of 4 m. © 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and peer-review under responsibility of Peer-review under responsibility o the SICE 2018 organizers. Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperatu o enclature Abstract The steels used for manufacturing nuclear reactor pressure vessel are low alloy ferritic steels. There is a range of temperatures at which these steels exhibit transition from ductile to brittle fracture known as the ductile to brittle transition temperature (DBTT). In these range of temperatures, ferritic steels exhibit a scatter in the fracture toughness values having a characteristic statistical distribution which is unique to ferritic steels. The master curve methodology aims to capture this behaviour of ferritic steels through fracture mechanics principles. To obtain master curve, fracture experiments of standard specimens as per ASTM E-1921 must be carried out. Since reactor pressure vessel steels suffer loss in ductility due to irradiation embrittlement during its service life, master curve needs to be generated at periodic intervals using surveillance specimens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear reactor for keeping these specimens are limited. Also, the radiation dose associated with testing standard sized irradiated specimens can be dangerous for the personnel involved. Under these circumstances, it becomes necessary to carry out such tests using miniaturized specimens. In this work, we will obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT specimens having a thickness of 4 mm. © 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperature a Reactor S fety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India Abstract The steels used for manufacturing nuclear reactor pressure vessel are low alloy ferritic steels. There is a ge of t er es at which these steels exhibit transition from ductile to brittle fracture known s the ductile to brittle tr nsition temperature (DBTT). In these range of temperatures, ferritic steels xhibit a sc t in th fracture t ughness values having a characteristic statistical distribution which is unique to ferritic teels. The master curve methodology ai s to capture this behaviour of ferritic steels through fracture mechanics principles. To obtain master curve, fracture experiments of standard specimens as per ASTM E-1921 must be carried out. Since reactor pressur vessel st els suffer lo s in ductility due to irradiation embrittlement uring its service life, master curve needs to be gene ated at periodic intervals using surveillance spe imens. Use of standard sized fracture specimens as surveillance specimens are difficult as the space available in a nuclear reactor for keeping these specimens are limited. Also, the radiation dose associated with testing standard sized irradiated specimens can be dangerous for the personnel involved. Under these circumstances, it becomes necessary to carry out such tests using miniaturized pecimens. I this wo k, we will obtain the fracture toughness master curve of 20MnMoNi55 teel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT specimens having a thickness of 4 mm. © 2018 The Authors. Published by Elsevier B.V. This is open access article under the CC BY-NC-ND license (https://creat vecommons.org/ icenses/by- c-nd/4.0/) Sel ction and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. Keywords: Master Curve; R actor Pressure Vessel; Duct le to brittle transition temperature a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India Abstract The steels used for manufacturing nuclear reactor pressure v ssel are low alloy ferritic steels. There is a range of temperatures at which these steels exhibit transition from ductile to brittle fracture known as the ductile to brittle transition temperature (DBTT). In these range of temperatures, ferritic steels exhibit a scatter in the fracture toughness values having a ch rac ristic statistical distribution which is unique to fe ritic steels. The master curve methodology aims to capture this behaviour of f rri ic steels through fractur m chanic principles. To o tai mas r curv , fracture experiments of standard as per ASTM E-1921 must be carried out. Since reactor pressure vessel steels suffer loss in duct lity due to irradiation embr ttlement during its service l f , mast r curve needs to be generated at periodic intervals using surveillan e spe . Use of stan ard ized fractu e specimens as surveillanc specimens are difficult as the space available in a nuclear reactor for keeping these specimens are limited. Also, the radiation dose associated with t sting standard sized irradiated specimens can be dangerous for the personn l involved. Under the e circumstances, it becomes nece sary to c rry out such tests using miniaturized specimens. In this work, we will obtain the fracture toughness master curve of 20MnMoNi55 steel (low alloy ferritic steel used for making nuclear reactor pressure vessels) from miniature CT specimens having a thickness of 4 mm. © 2018 The Authors. Published by Elsevier B.V. This is an open access ar icle under the CC BY-NC-ND license (https://creativecommons.org/licens s/by-nc-nd/4.0/) S l ion and peer- eview under responsibility of Peer-r view under responsibility of the SICE 2018 organizers. Keywords: M st r Curve; Reactor Pressure Vessel; Ductile to rittl transit on temp rature a Reactor S fety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India © 2018 The Authors. Published by Elsevier B.V. This is an open access article un the CC BY-NC-ND license (https://creat vecommons.org/licenses/by- c-nd/4.0/) Selection and peer-r view nder responsib lity of P er-review und r respons bi ity of the SICE 2018 organizers. © 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. © 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creat vecommons.org/licenses/by- c-nd/4.0/) Selectio and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. © 2018 The Authors. Published by Elsevier B.V. This is a open access article under the - - license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and pee -review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. © 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selectio and peer-review under responsibility of Peer-review u der responsibility of the SICE 2018 organizers. © 2016 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Scientific Committee of PCF 2016. Thickness of CT specimen Remaining ligament of CT spe imen Crack length of the fracture speci en B Thickness of CT speci en Remaining liga ent of CT specimen Nomenclature a Crack length of the fracture specimen B Thickness of CT specimen Remaining ligament of CT specimen Nomenclature a Crack l ngth of the fracture specimen B Thickness of CT specimen Remaining ligament of CT specimen Nomenclature a Crack length of the fracture specimen Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperature Cra length of the fracture specimen Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperature Nomenclature a Crack length of the fracture specimen Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperature Keywords: Master Curve; Reactor Pressure Vessel; uctile to brittle transition te perature Keywords: Master Curve; Reactor Pressure Vessel; Ductile to brittle transition temperature Keywords: High Pressure Turbine Blade; Creep; Finite Element Method; 3D Model; Simulation. Stress intensity factor Young’s Modulus Young’s Modulus B Thickness of CT specimen a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India a Reactor Safety Division, BARC-Trombay, Mumbai 40008, India b Materials Group, BARC-Trombay, Mumbai 400085, India Nomenclature a Crack length of the fracture specimen Nomenclature a www.elsevier.com/locate/procedia

B b E K a b E b E K b E K b E K E K B b E K B b E K B b E K B b E K J J J J J el J pl N � J el J pl N r CT P L � J el J pl N r CT P L � J e J pl N r CT P L � J J el J pl N r P L � J el J pl N CT P L � J J el J pl r CT J � J N � J N

Young’s Modulus oung’s odulus Stress intensity factor Stress intensity factor Stress intensity factor Remaining ligament of CT specimen Remaining ligament of CT specimen Thickness of CT specimen Remaining ligament of CT specimen Cra k l ngth of the fracture specimen Thickness of CT specimen Remaining ligament of CT specimen rack length of the fracture specimen Thickness of CT sp cimen Remaining ligament of CT specimen Crack length of the fracture specimen Thickness of CT specimen Remaining ligament of CT specimen

* Corresponding author. Tel.: +351 218419991. E-mail address: amd@tecnico.ulisboa.pt Yield Stress Yield Stress Limit Load Yield Stress No. of valid tests CT Total no. of fracture tests r No. of valid tests Plastic part of J-Integral N Total no. of fracture tests No. of valid tests e Ela of J-Integral J pl Plastic part of J-Int gral N Total no. of fracture tests J el lastic p rt of J-Integral J pl Plastic part of J-Integral otal no. of fracture tests J-Integral J el Elastic p rt of J-Integral J pl Plastic part of J-Integral Elastic part of J-Integral Plastic part of J-Integral Total no. of fracture tests Elastic part of J-Integral Plastic part of J-Integral Total no. of fracture tests Elastic part of J-Integral Plastic part of J-Integral Total no. of fracture tests E t o J e l Plastic part of J-Integral Total no. of fracture tests J-Integral Elastic part of J-Integral Plastic part of J-Integral Total no. of fracture t sts Stress intensity factor J-Integral El ti t o te r l Plastic part of J-Integral Stress intensity factor J-Integr l Elastic part of J-Integral Young’s Modulus Stress intensity factor J-Integral Young’s Modulus Stress intensity factor J-Integral Young’s M dulus Stress intensity facto r No. of valid tests No. of valid tests No. of valid tests No. of valid tests CT P L Limit Load Yield Stress Limit Load Limit Load J-Integral J-Integral J-Integral J-Integral Young’s Modulus Stress intensity factor B Thickness of CT specimen b Young’s Modulus Young’s Modulus Nomenclature a Nomenclature a Nomenclature a

Compact Tension Specimen (Fracture specimen) Compact Tension Speci en (Fracture speci en) Compact Tension Specimen (Fracture specimen) Compact Tension Specimen (Fracture specimen)

2452-3216 © 2016 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Scientific Committee of PCF 2016. 2452-3216  2019 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (https://creativecommons.org/licenses/by-nc-nd/4.0/) Selection and peer-review under responsibility of Peer-review under responsibility of the SICE 2018 organizers. 10.1016/j.prostr.2019.05.049 * Corresponding Author: Tel: 022-25596871 * Corresponding Author: Tel: 022-25596871 * Corresponding Author: Tel: 022-25596871 * Corresponding Autho : Tel: 022-25596871 Yield Stress * Corresponding Author: Tel: 022-25596871 Limit Load Yield Stres * Corresponding Author: Tel: 022-25596871 Compact Tension Specimen (Fracture specimen) P L Limit Load � Yield S res r N . of valid tests CT Compact Tension Specimen (Fracture specimen) P L Limit Load Yield Stress r No. of valid tests CT o pact Tension Specimen (Fracture specimen) P L i it oad ield Stress Total no. of fracture tests r No. of valid tests CT Compact Tension Specime (Fracture sp cimen) P L Limit Load � Yield Stress * Corresponding Author: Tel: 022-25596871 Compact Tension Specimen (Fracture specimen) Compact Tension Specimen (Fracture specimen) Limit Load * Corresponding Author: Tel: 022-25596871 * Corresponding Author: Tel: 022-25596871 * Corresponding uthor: Tel: 022-25596871