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  4. Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region
 
conference paper

Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region

Spätig, Philippe  
•
Mazánová, V.
•
Suman, S.
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December 13, 2019
Key Engineering Materials
18th International Conference on Fracture and Damage Mechanics

Three point bending and impact tests with sub-sized Charpy specimens were performed on the JRQ reference steel for reactor pressure vessels. Quasi-static and dynamic fracture toughness data were calculated and the fracture behavior in the ductile to brittle transition region was evaluated within the frame of the master curve method (ASTM E1921). Specimens with shallow and deep cracks were studied and the respective influence of crack length and loading rate on the reference transition temperature was determined. The force-time curves of specimens with shallow cracks presented significantly smaller oscillations with respect to the absolute force, making the fracture toughness evaluation more accurate.

  • Details
  • Metrics
Type
conference paper
DOI
10.4028/www.scientific.net/KEM.827.294
Author(s)
Spätig, Philippe  
Mazánová, V.
Suman, S.
Seifert, Hans Peter
Date Issued

2019-12-13

Published in
Key Engineering Materials
Volume

827

Start page

294

End page

299

Subjects

Constraint Loss

•

Dynamic Fracture Toughness

•

Master-Curve Method

•

Quasi-Static Fracture Toughness

•

Reactor Pressure Vessel Steels

Editorial or Peer reviewed

REVIEWED

Written at

OTHER

EPFL units
LRS  
Event name
18th International Conference on Fracture and Damage Mechanics
Available on Infoscience
April 28, 2020
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/168428
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