PSI - Issue 2_A

ScienceDirect Available online at www.sciencedirect.com Av ilable o line at ww.sciencedire t.com ScienceDirect Structural Integrity Procedia 00 (2016) 000 – 000 Procedia Struc ural Integrity 2 (2016) 3562–3568 Available online at www.sciencedirect.com ScienceDirect Structural Integrity Procedia 00 (2016) 000–000 Available online at www.sciencedirect.com Sci nceDirect Structural Integrity Procedia 00 (2016) 000–000

www.elsevier.com/locate/procedia

www.elsevier.com/locate/procedia www.elsevier.com/locate/procedia

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. 21st European Conference on Fracture, ECF21, 20-24 June 2016, Catania, Italy Fatigue strength of PF-1 coil helium inlet with weld defects . Kazantsev A.G. a, * , Kakhadze M.G. a , Soin K.A. a , Rodin I.Y. b , Nasluzov S.N. b a TSNIITMASH, Sharikopodshipnikovskaya, 4, Moscow 115088, Russia; b NIIEFA, Metallostroy, 3, St. Petersburg 196641, Russia. Helium inlet (HI), used for supply of liquid helium into a superconductor, is a critical element of PF-1 coil of the fusion reactor ITER. The superconductor is placed into internal bore of a steel jacket. TIG welding without subsequent heat treatment is used for connection the HI to the jacket. Deviations from the established technology of welding may cause some crack-like defects. Therefore possibility of occurrence the through wall cracks and inlet leak under cyclic loading was evaluated. Calculations of growth of initial weld defects with various depths under cyclic loading were performed using Paris equation. It was obtained that critical size of initial defects, which can growth up to through wall after 30,000 cycles is about 1 mm. For experimental study a cyclic strength and tightness fatigue tests of full-scale 1.5 m length sample of helium inlet have been conducted in liquid nitrogen (77K). Visual control, leak testing, X-ray and liquid penetration inspections were performed after passing the given base test 30,000 cycles. Defects were not found by all used control methods. R eliability of the adopted welding technology was confirmed. Keywords: ITER; helium inlet; weld joint; residual stress; fa igue; cyclic l ading; cryostat; The paper presents design and experimental study of cyclic strength and tightness of welding helium inlet to the jacket of the superconductor coils PF1 of magnetic system of the thermonuclear reactor (ITER). Helium inlet used for supplying liquid helium into the superconductor, is one of the critical structural elements of the design. The jacket (austenitic stainless steel 316L) of the superconductor has a square cross section with an internal channel diameter of about 40mm to accommodate the superconductor and circulation of liquid helium, fig.1. Helium inlet connection with the jacket is carried out TIG welding with filler Cr19-Ni9 wire without a subsequent heat treatment. To reduce the stress concentration in the weld transition to the flat surface of the jacket it has a shaped fillet with a radius of about 6 mm. 21st European Conference on Fracture, ECF21, 20-24 June 2016, Catania, Italy Fatigue str gth of PF-1 coil helium inlet with weld defects . Kazantsev A.G. a, * , Kakhadze M.G. a , Soin K.A. a , Rodin I.Y. b , Nasluzov S.N. b a TSNIITMASH, Sharikopodshipnikovskaya, 4, Moscow 115088, Russia; b NIIEFA, Metallostroy, 3, St. Petersburg 196641, Russia. Abstract Helium inlet (HI), used for supply of liquid helium into a superco ductor, is a critical element of PF-1 coil of the fusion reactor ITER. The superconductor is placed into internal bore of a steel jacket. TIG welding without subsequent heat treatment is used for connection the HI to the jacket. Deviations from the established technology of welding may cause some crack-like defects. Therefore possibility of occurrence the through wall cracks and inlet leak under cyclic loading was evaluated. Calculations of growth of initial weld defects with various dep hs under cyclic loading were performed using Paris equation. It was obtained that critical size of initial defects, which can growth up to through wall after 30,000 cycles is about 1 mm. For experimental study a cyclic strength and tightness fatigue tests of full-scale 1.5 m length sample of helium inlet have been conducted in liquid nitrogen (77K). Visual control, leak testing, X-ray and liquid penetration inspections were performed after passing the given base test 30,000 cycles. Defects were not found by all used control methods. R eliability of the adopted welding technology was confirmed. Keywords: ITER; elium inlet; weld joint; residual stress; fatigue; cyclic loading; cryostat; The paper pr sents design and experimental study of yclic streng h and tightness of welding helium inlet to the jacket of the superconductor coils PF1 of magnetic system of the thermonuclear reactor (ITER). Helium inlet used for supplying liquid helium into the superconductor, is one of the critical structural elements of the design. The jacket (austenitic stainless steel 316L) of the superconductor has a square cross section with an internal channel diameter of about 40mm to accommodate the superconductor and circulation of liquid helium, fig.1. Helium inlet connection with the jacket is carri d out TIG welding with filler Cr19-Ni9 wire without a subsequent heat treatment. To reduce the stress conc ntr tion in the weld transition to the flat surface of the jacket it has a shaped fillet with a radius of about 6 mm. Copyright © 2016 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/). Peer-review under responsibility of the Scientific Committee of ECF21. © 2016 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Scientific Committee of PCF 2016. Keywords: High Pressure Turbine Blade; Creep; Finite Element Method; 3D Model; Simulation. Abstract

* Corresponding author. Tel.: +7-985-773-2702; fax: +7-495-675-89-05. E-mail address: kazantsev@cniitmash.com

* Corresponding author. Tel.: +351 218419991. E-mail address: amd@tecnico.ulisboa.pt * Corresponding author. Tel.: +7-985-773-2702; fax: +7-495-675-89-05. E-mail address: kazantsev@cniitmash.com 2452-3216 © 2016 The Authors. Published by Elsevier B.V. Peer review under responsibility of t e Scientific Committee of ECF21.

2452-3216 © 2016 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Scientific Committee of PCF 2016. Copyright © 2016 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license ( http://creativecommons.org/licenses/by-nc-nd/4.0/ ). Peer review under responsibility of the Scientific Committee of ECF21. 10.1016/j.prostr.2016.06.444 2452-3216 © 2016 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Scientific Committee of ECF21.