PSI - Issue 42

Available online at www.sciencedirect.com Structural Integrity Procedia 00 (2019) 000 – 000 tr t r l I t rit r i ( ) Available online at www.sciencedirect.com ^ĐŝĞŶĐĞ ŝƌĞĐƚ il l li t . i i t.

www.elsevier.com/locate/procedia . l i r. /l t / r i

ScienceDirect

Procedia Structural Integrity 42 (2022) 218–223

© 2022 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) Peer-review under responsibility of the scientific committee of the 23 European Conference on Fracture – ECF23 Abstract The nuclear industry demands analyses that make possible the long-term operation of nuclear power plants (i.e., beyond 40 years). In this sense, one of the main challenges to overcome is the restricted amount of material available to extend the surveillance programs. To mitigate this issue, mini-CT specimens have been proposed for the evaluation of the fracture properties of reactor pressure vessel (RPV) materials, and particularly, the corresponding Master Curve. These specimens can be taken from the broken halves of previously tested Charpy specimens. In this work, mini-CT specimens have been employed to evaluate the reference temperature of the RPV ANP-5 steel in non-irradiated conditions. The results were compared with those obtained by means of conventional fracture tests. © 2020 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 23 European Conference on Fracture - ECF23 Keywords: 1. Introduction The monitoring of the reactor pressure vessel (RPV) materials is an indispensable prerequisite for the safe operation of nuclear power plants (NPPs). RPVs are usually made of bainitic ferritic steels which tend to become increasingly brittle when subjected to neutron irradiation. Moreover, this irradiation also leads to an increase in the ductile-to brittle transition temperature and therefore the long-term monitoring of these materials is essential. Surveillance programmes are based on the observation of changes in the mechanical properties of structural materials that limit l i t l t t i l t l t ti l l t i. ., . t i , t i ll t i t t i t t t i l il l t t t ill . iti t t i i , i i i t l ti the fracture properties of reactor pressure vessel (RPV) materials, ti l l , t i t . i t t l i l t t i . t i , i i i l t l t t t t t t l i i i t iti . lt it t t i ti l t t t . t . li l i . . This is an open access article un t li tt :// ti . /li / / . / i i ilit t : . i it i t t l t i l i i i l i it t ti l l t . ll i iti iti t l i t t i i l ittl j t t t i i ti . , t i i i ti l l t i i t til t ittl t iti t t t t l t it i t t i l i ti l. ill t ti i t i l ti t t l t i l t t li it 23 European Conference on Fracture - ECF23 Master curve evaluation of ANP-5 steel using mini-CT specimens Marcos Sánchez a *, Sergio Cicero a , Borja Arroyo a , Sergio Arrieta a a LADICIM (Laboratory of Materials Science and Engineering), University of Cantabria, E.T.S. de Ingenieros de Caminos, Canales y Puertos, Av/Los Castros 44, Santander 39005, Spain Master curve evaluation of ANP-5 steel using mini-CT specimens a a a a a I I ( t f t i l i i i ), i it f t i , . . . I i i , l t , / t , t , i

* Corresponding author. E-mail address: sanchezmam@unican.es i t r. - il : i . rr

2452-3216 © 2020 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 23 European Conference on Fracture - ECF23 l i r . . i i rti l r t - - li ( tt :// r ti . r /li / - - / . /) i i ilit t - t r . li

2452-3216 © 2022 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) Peer-review under responsibility of the scientific committee of the 23 European Conference on Fracture – ECF23 10.1016/j.prostr.2022.12.027