To face the future challenge of global energy supply, taking into account the depletion of fossil fuels and global warming issues, the main nuclear energy users are strongly involved in a research program to fourth-generation reactor technology. This new generation will work at high temperatures between about 450 °C and 550 °C. Extensive studies have been launched worldwide to assess steel grades able to meet these new operating conditions. One of the candidates is Vanadium enhanced 9% Chromium steel grade (EN 10028-2 X11CrMoVNb 9-1 – ASTM A387 grade 91 class 2 – ASME SA387 grade 91 class 2). To meet the future needs in nuclear energy, Industeel improved its conventional 9Cr1MoVNb steel devoted to the fabrication of steam lines in thermal power plants. Preliminary studies revealed the feasibility of thick plates in this enhanced grade. Thick plates, 140 and 210 mm thick, have been hot rolled from a 82 metric tons ingot. Welded joints have then been prepared. Tests performed on both base metal and welded zones proved the excellent mechanical properties of the grade, especially regarding toughness property. This work demonstrated the industrial feasibility of very thick plates made of grade 91 for nuclear applications. This contribution is a review of the work done as well as the results obtained on the plates.
Skip Nav Destination
ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
July 18–22, 2010
Bellevue, Washington, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-49255
PROCEEDINGS PAPER
Thick Plates in Grade 91 for Fourth Generation Nuclear Reactors Available to Purchase
Sylvain Pillot,
Sylvain Pillot
ArcelorMittal, R&D Le Creusot - Industeel, Le Creusot, France
Search for other works by this author on:
Zhao Zhao,
Zhao Zhao
ArcelorMittal, R&D Le Creusot - Industeel, Le Creusot, France
Search for other works by this author on:
Ste´phanie Corre,
Ste´phanie Corre
ArcelorMittal, R&D Le Creusot - Industeel, Le Creusot, France
Search for other works by this author on:
Ce´dric Chauvy,
Ce´dric Chauvy
Industeel Arcelormittal, Rive de Gier, France
Search for other works by this author on:
Lionel Coudreuse,
Lionel Coudreuse
Industeel Arcelormittal, Rive de Gier, France
Search for other works by this author on:
Patrick Toussaint
Patrick Toussaint
Industeel Arcelormittal, Charleroi, Belgium
Search for other works by this author on:
Sylvain Pillot
ArcelorMittal, R&D Le Creusot - Industeel, Le Creusot, France
Zhao Zhao
ArcelorMittal, R&D Le Creusot - Industeel, Le Creusot, France
Ste´phanie Corre
ArcelorMittal, R&D Le Creusot - Industeel, Le Creusot, France
Ce´dric Chauvy
Industeel Arcelormittal, Rive de Gier, France
Lionel Coudreuse
Industeel Arcelormittal, Rive de Gier, France
Patrick Toussaint
Industeel Arcelormittal, Charleroi, Belgium
Paper No:
PVP2010-25628, pp. 847-860; 14 pages
Published Online:
January 10, 2011
Citation
Pillot, S, Zhao, Z, Corre, S, Chauvy, C, Coudreuse, L, & Toussaint, P. "Thick Plates in Grade 91 for Fourth Generation Nuclear Reactors." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B. Bellevue, Washington, USA. July 18–22, 2010. pp. 847-860. ASME. https://doi.org/10.1115/PVP2010-25628
Download citation file:
24
Views
Related Proceedings Papers
Related Articles
Effect of Weld Cooling Rates on Mechanical and Metallurgical Properties of Submerged Arc Welded Pressure Vessel Steel
J. Pressure Vessel Technol (August,2018)
Effect of Different Arc Welding Processes on the Metallurgical and Mechanical Properties of Ramor 500 Armor Steel
J. Eng. Mater. Technol (April,2020)
Crack Arrest Toughness of a Heat-Affected Zone Containing Local
Brittle Zones
J. Offshore Mech. Arct. Eng (November,1996)
Related Chapters
Materials
Power Boilers: A Guide to the Section I of the ASME Boiler and Pressure Vessel Code, Second Edition
Estimation of K Ic from Slow Bend Precracked Charpy Specimen Strength Ratios
Developments in Fracture Mechanics Test Methods Standardization
Introduction
Nuclear Reactor Thermal-Hydraulics: Past, Present and Future