Microstructural Evolution of Zr1NbxSnyFe Alloys Irradiated in a PWR at High Fluence: Influence of Iron and Tin-Reference-Cited by-同舟云学术

Microstructural Evolution of Zr1NbxSnyFe Alloys Irradiated in a PWR at High Fluence: Influence of Iron and Tin

Published:2023-11-01 Issue: Volume: Page:568-598
ISSN:
Container-title:Zirconium in the Nuclear Industry: 20th International Symposium
language:
Short-container-title:

Author:

Doriot Sylvie¹^ORCID,Verhaeghe Bénédicte²^ORCID,Toffolon-Masclet Caroline¹^ORCID,Bossis Philippe³^ORCID,Bourlier Florent⁴^ORCID,Ton-That Marc⁵^ORCID,Ambard Antoine⁶^ORCID

Affiliation:

1. Université Paris-Saclay, CEA, Service de Recherches Métallurgiques Appliquées, 91191 Gif-sur-Yvette Cedex, FR

2. Université Paris-Saclay, CEA, Service d’Etudes des Matériaux Irradiés, 91191 Gif-sur-Yvette Cedex, FR

3. Université Paris-Saclay, CEA, Département des Matériaux pour le Nucléaire, 91191 Gif-sur-Yvette Cedex, FR

4. Framatome, Fuel Business Unit, 2 rue du Professeur Jean Bernard, 69007 Lyon, FR

5. Electricité de France, DIPNN/Direction Technique, 19 rue Pierre Bourdeix, 69007 Lyon, FR

6. Electricité de France, R&D Division, Materials and Mechanics of Components, Les Renardières, 77818 Moret sur Loing Cedex FR

Publisher

ASTM International

Reference35 articles.

1. V. Chabretou, P. B. Hoffmann, S. Trapp-Pritsching, G. Garner, P. Barberis, V. Reyberolle, and J. J. Vermoyal, “Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth and Mechanical Properties,” in Zirconium in the Nuclear Industry: 16th International Symposium, ed. P. Barberis (West Conshohocken, PA: ASTM International, 2012), 801–826, https://doi.org/10.1520/STP152920120032

2. V. Chabretou and S. Trapp-Pritsching, “Q12 Ultra Low Tin Quaternary Alloy for Structural Components in PWR Fuel Assemblies” (paper presentation, Topfuel 2015, Zurich, Switzerland, September 17–18, 2015).

3. S. Yagnik, R. Adamson, G. Kobylyansky, J. H. Chen, D. Gilbon, S. Ishimoto, T. Fukuda, L. Hallstadius, A. Obukhov, and S. Mahmood, “Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation Induced Growth Behavior of Zirconium Alloy Variants,” in Zirconium in the Nuclear Industry: 18th International Symposium, ed. R. J. Comstock and A. J. Motta (West Conshohocken, PA: ASTM International, 2018), 748–795, https://doi.org/10.1520/STP159720160040

4. V. N. Shishov, “The Evolution of Microstructure and Deformation Stability in Zr-Nb-(Sn,Fe) Alloys under Neutron Irradiation,” in Zirconium in the Nuclear Industry: 16th International Symposium, ed. P. Barberis (West Conshohocken, PA: ASTM International, 2012), 37–66, https://doi.org/10.1520/STP152920120003

5. D. Gilbon, A. Soniak, S. Doriot, and J. P. Mardon, “Irradiation Creep and Growth Behaviour, and Microstructural Evolution of Advanced Zr-Base Alloys,” in Zirconium in the Nuclear Industry: Twelfth International Symposium, ed. G. P. Sabol and G. D. Moan (West Conshohocken, PA: ASTM International, 2000), 51–73, https://doi.org/10.1520/STP14294S