PSI - Issue 13

ScienceDirect Available online at www.sciencedirect.com Av ilable o line at ww.sciencedire t.com ienceDirect Structural Integrity Procedia 00 (2016) 000 – 000 Procedia Structural Integrity 13 (2018) 2083–2 88 Available online at www.sciencedirect.com ScienceDirect Structural Integrity Procedia 00 (2018) 000 – 000 Available online at www.sciencedirect.com ScienceDirect Structural Integrity Procedia 00 (2018) 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. ECF22 - Loading and Environmental effects on Structural Integrity Pressurized Thermal Shock analysis of the reactor pressure vessel Peter Trampus* Professor emeritus, H-2401 Dunaújváros, University of Dunaújváros, Hungary PTS analysis is a substantial part of the technical analyses supporting the license application for operation beyond design life. Guidance for the analysis’ concept is given by the Hungarian nuclear regulator which is in line with the relevant international rules. Involving technical support organizations and independent consultants as well as taking into account the changes in fuel management Paks NPP, Hungary, compiled a new PTS analysis. Subjects of the analysis were the RPV belt line region components as well as other circumferential welds of the RPV including nozzle region. Beyond the PTS initiating events selected on the basis of engineering judgment a PSA provided additional transients which showed a higher frequency than 10 -5 /year. Thermal-hydraulic calculations completed for each selected PTS initiating event provided the necessary input for the structural analysis. Based on core configurations end-of-life fluence were calculated. Neutron dosimetry surveillance results were used to verify the calculations. Temperature and stress field calculations were performed by solving the system of equations of elasticity. Underclad crack was postulated for fracture mechanics calculation . K I was calculated at the crack tip and the boundary between the cladding and base / weld metal; K Ic was calculated on the basis of the reference curve. Comparison of these two parameters ( K I ≤ K Ic ), i.e. evaluation of whether the postulated defect stability criteria was met, gave the result. © 2018 The Authors. Published by Elsevier B.V. Peer-review und r responsibility of the ECF22 organizers. Keywords: lif extension; pressurized therm l shock; plant transients; fast neutron fluence; linear elastic fracture mechanics; underclad crack. At the end of 2017, the service life extension licensing process of the four VVER-440/V-213 units at Paks NPP, Hungary, was completed. According to the legislation a formal license application for the extended period was submitted to the nuclear regulator in which th safe operati n had to be demonstrated for the extended term. To justify the feasibility of the planned new operation period (20 years), the extension of the original Time-Limited Ageing © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ECF22 organizers. ECF22 - Loading and Environmental effects on Structural Integrity Pressurized Thermal Shock analysis of the reactor pressure vessel Peter Trampus* Professor emeritus, H-2401 Dunaújváros, University of Dunaújváros, Hungary Abstract PTS analysis is a substantial part of the technical analyses supporti g the license application for operation beyond design life. Guid ce for the analysis’ concept is given by the Hu garian n clear re ulator which is in line with the releva t international rules. Involving tec nical support organizatio s and independent consultants as well as tak g into account the changes in fuel management Paks NPP, Hunga y, compiled a ew PTS a alysis. Subjects of the analysis were the RPV belt line region components as well as other circumfere ti l welds of the RPV including nozzle region. Beyond the PTS initiating events sel cted on the basi of engineering judg ent a PSA provided additional transients which showed a higher frequency tha 10 -5 /year. Thermal-hydraulic calculations completed for each selected PTS initiating event provided the necessary input for the structur l analysis. Based on ore configurations en -of-life flu nce were calculated. N utron d s metry surveillance res lts were u ed to verify the calculations. Temperature nd tress field ca culations were performed by solving the ystem of equations of la ticity. Underclad rack was postulated for fracture mechanics calculation . K I was calculated at the crack tip and the boundary between the cladding and base / weld m tal; K Ic was calculated on the b sis of the reference curve. Comparison of these two parameters ( K I ≤ K Ic ), i.e. evalu tion of whether the p stul ted defect stability criteria was m t, gave the r sult. © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of th ECF22 org niz rs. Keywor s: life xtension; pressurized thermal shock; pl nt tran ients; fast neutron fluence; linear elastic fracture mechanics; underclad crack. 1. Introduction At the end of 2017, the service life extension licensing process of the four VVER-440/V-213 units at Paks NPP, Hungary, was completed. According to the legislation a formal license application for the extended period was submitted to the nuclear regulator in which the safe operation had to be demonstrated for the extended term. To justify the feasibility of the planned new operation period (20 years), the extension of the original Time-Limited Ageing © 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 1. Introduction

* Corresponding author. Tel.: +36-20-985-5970 E-mail address: trampus@uniduna.hu * Corresponding author. Tel.: +36-20-985-5970 E-mail ad ress: trampus@uniduna.hu

* Corresponding author. Tel.: +351 218419991. E-mail address: amd@tecnico.ulisboa.pt 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ECF22 organizers. 2452-3216 © 2018 The Authors. Published by Elsevier B.V. Peer review under r sponsibility of the ECF22 organizers.

2452-3216 © 2016 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the Scientific Committee of PCF 2016.

2452-3216  2018 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ECF22 organizers. 10.1016/j.prostr.2018.12.204