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Title: Selection of materials for sodium fast reactor steam generators

Abstract

Sodium Fast Reactor (SFR) is considered in France as the most mature technology of the different Generation IV systems. In the short-term the designing work is focused on the identification of the potential tracks to demonstrate licensing capability, availability, in-service inspection capability and economical performance. In that frame materials selection for the major components, as the steam generator, is a particularly key point managed within a French Research and Development program launched by AREVA, CEA and EDF. The choice of the material for the steam generator is indeed complex because various aspects shall be considered like mechanical and thermal properties at high temperature, interaction with sodium on one side and water and steam on the other side, resistance to wastage, procurement, fabrication, weldability and ability for inspection and in-situ intervention. The following relevant options are evaluated: the modified 9Cr1Mo ferritic-martensitic grade and the Alloy 800 austenitic grade. The objective of this paper is to assess for both candidates their abilities to reach the current SFR needs regarding material design data, from AFCEN RCC-MRx Code in particular, compatibility with environments and manufacturability. (authors)

Authors:
; ;  [1];  [2]; ;  [3]
  1. AREVA (France)
  2. Commissariat a l'energie atomique et aux energies alternatives - CEA (France)
  3. Electricite de France - EDF (France)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22107896
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 14 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; AUSTENITIC STEELS; DESIGN; FAST REACTORS; FERRITIC STEELS; FRANCE; INCOLOY 800; IN-SERVICE INSPECTION; LICENSING; MARTENSITIC STEELS; SODIUM; SODIUM COOLED REACTORS; STEAM GENERATORS; TEMPERATURE RANGE 0400-1000 K; THERMODYNAMIC PROPERTIES

Citation Formats

Dubiez-Le Goff, S., Garnier, S., Gelineau, O., Dalle, F., Blat-Yrieix, M., and Augem, J. M. Selection of materials for sodium fast reactor steam generators. United States: N. p., 2012. Web.
Dubiez-Le Goff, S., Garnier, S., Gelineau, O., Dalle, F., Blat-Yrieix, M., & Augem, J. M. Selection of materials for sodium fast reactor steam generators. United States.
Dubiez-Le Goff, S., Garnier, S., Gelineau, O., Dalle, F., Blat-Yrieix, M., and Augem, J. M. Sun . "Selection of materials for sodium fast reactor steam generators". United States.
@article{osti_22107896,
title = {Selection of materials for sodium fast reactor steam generators},
author = {Dubiez-Le Goff, S. and Garnier, S. and Gelineau, O. and Dalle, F. and Blat-Yrieix, M. and Augem, J. M.},
abstractNote = {Sodium Fast Reactor (SFR) is considered in France as the most mature technology of the different Generation IV systems. In the short-term the designing work is focused on the identification of the potential tracks to demonstrate licensing capability, availability, in-service inspection capability and economical performance. In that frame materials selection for the major components, as the steam generator, is a particularly key point managed within a French Research and Development program launched by AREVA, CEA and EDF. The choice of the material for the steam generator is indeed complex because various aspects shall be considered like mechanical and thermal properties at high temperature, interaction with sodium on one side and water and steam on the other side, resistance to wastage, procurement, fabrication, weldability and ability for inspection and in-situ intervention. The following relevant options are evaluated: the modified 9Cr1Mo ferritic-martensitic grade and the Alloy 800 austenitic grade. The objective of this paper is to assess for both candidates their abilities to reach the current SFR needs regarding material design data, from AFCEN RCC-MRx Code in particular, compatibility with environments and manufacturability. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
Other availability
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