Development and Status of Embrittlement Trend Correlations in France-Reference-Cited by-同舟云学术

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Development and Status of Embrittlement Trend Correlations in France

Published:2023-06-01 Issue: Volume: Page:144-158
ISSN:
Container-title:Radiation Embrittlement Trend Curves and Equations and Their Use for RPV Integrity Evaluations
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Author:

Todeschini Patrick¹^ORCID,Jourdain William²,Jeuland Kevin³,Jardin Nicolas⁴,Dal Bianco Christophe⁵,Massoud Jean-Paul⁵

Affiliation:

1. EDF-R&D, MMC Department, EDF Lab Les Renardières, Moret-Sur-Loing, 77250, FR

2. EDF-DI, 2 Rue Ampère, Saint-Denis, 93200, FR

3. EDF-DI, LIDEC, CNPE de Chinon, Avoine, 37420, FR

4. EDF-UNIE, 1 Place Pleyel, Saint Denis, 93200, FR

5. EDF-DT, 19 Rue Pierre Bourdeix, Lyon, 69007, FR

Publisher

ASTM International

Reference18 articles.

1. P. Todeschini, L. Pineau, B. Courtois, Y. Shen, M. E. Gharbaoui, and N. Jardin, “Experience Gained in Reactor Pressure Vessel Surveillance Programs in France,” International Review of Nuclear Reactor Pressure Vessel Surveillance Programs, ed. W. L. Server and M. Brumovský (West Conshohocken, PA: ASTM International, 2018), 184–201, https://doi.org/10.1520/STP160320170143

2. Design and Construction Rules for Mechanical Components of PWR Nuclear Islands, RCC-M 2017 (Courbevoie, France: AFCEN, 2017).

3. In-Service Inspection Rules for Mechanical Components of PWR Nuclear Islands, RSE-M 2020 (Courbevoie, France: AFCEN, 2020).

4. Revision of the Irradiation Embrittlement Correlation Used for the EDF RPV Fleet;Todeschini;Fontevraud 7. Les Matériaux dans le Nucléaire

5. C. Brillaud and F. Hedin, “In-Service Evaluation of French Pressurized Water Reactor Vessel Steel,” in Effects of Radiation on Materials: 15th International Symposium, ed. R. E. Stoller, A. S. Kumar, and D. S. Gelles (West Conshohocken, PA: ASTM International, 1992), 23–49.

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