Deformation under irradiation of 304L and 316 austenitic stainless steels

J. Garnier; P. Dubuisson; M. Delnondedieu; J. P. Massoud; Y. Bréchet; S. Leclercq; J. Besson; P. Scott; X. Averty; F. Rozenblum

Deformation under irradiation of 304L and 316 austenitic stainless steels

J. Garnier, P. Dubuisson, M. Delnondedieu, J. P. Massoud, Y. Bréchet, S. Leclercq, J. Besson, P. Scott, X. Averty, F. Rozenblum

Research output: Chapter in Book/Report/Conference proceeding › Conference Paper › Other

4 Citations (Scopus)

Abstract

SA304L and CW316 stainless steels are the constitutive materials of the core internals of French Pressurized Water Reactors. In order to study the effects of irradiation on the austenitic stainless steels deformation, swelling mandrel tubes with different ceramics were irradiated in the core of OSIRIS reactor around 10dpa. Experiments have been carried out in PWR water and in inert NaK environment. A comprehensive experimental study of irradiation creep at 330°C for doses up to 120dpa and stresses between 127 and 200MPa is provided for both alloys. In order to assess stress and strain evolutions in the swelling mandrel tube, a constitutive law is proposed. This law is based on a large database of post irradiation mechanical tests and in pile creep tests on pressurized tubes performed on steels representative of French PWR internals. This provides a necessary step in a comprehensive study of behavior under simultaneous stress and irradiation.

Original language	English
Title of host publication	Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Pages	241-253
Number of pages	13
Publication status	Published - 2007
Externally published	Yes
Event	International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 - Whistler, Canada Duration: 19 Apr 2007 → 23 Apr 2007 Conference number: 13th

Publication series

Name	Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Volume	1

Conference

Conference	International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Country/Territory	Canada
City	Whistler
Period	19/04/07 → 23/04/07

Cite this

Garnier, J., Dubuisson, P., Delnondedieu, M., Massoud, J. P., Bréchet, Y., Leclercq, S., Besson, J., Scott, P., Averty, X., & Rozenblum, F. (2007). Deformation under irradiation of 304L and 316 austenitic stainless steels. In Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 (pp. 241-253). (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007; Vol. 1).

Garnier, J. ; Dubuisson, P. ; Delnondedieu, M. et al. / Deformation under irradiation of 304L and 316 austenitic stainless steels. Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 2007. pp. 241-253 (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007).

@inproceedings{9d73453a09984422bdb48c44c98a1f0b,

title = "Deformation under irradiation of 304L and 316 austenitic stainless steels",

abstract = "SA304L and CW316 stainless steels are the constitutive materials of the core internals of French Pressurized Water Reactors. In order to study the effects of irradiation on the austenitic stainless steels deformation, swelling mandrel tubes with different ceramics were irradiated in the core of OSIRIS reactor around 10dpa. Experiments have been carried out in PWR water and in inert NaK environment. A comprehensive experimental study of irradiation creep at 330°C for doses up to 120dpa and stresses between 127 and 200MPa is provided for both alloys. In order to assess stress and strain evolutions in the swelling mandrel tube, a constitutive law is proposed. This law is based on a large database of post irradiation mechanical tests and in pile creep tests on pressurized tubes performed on steels representative of French PWR internals. This provides a necessary step in a comprehensive study of behavior under simultaneous stress and irradiation.",

author = "J. Garnier and P. Dubuisson and M. Delnondedieu and Massoud, {J. P.} and Y. Br{\'e}chet and S. Leclercq and J. Besson and P. Scott and X. Averty and F. Rozenblum",

year = "2007",

language = "English",

isbn = "9781605600598",

series = "Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007",

pages = "241--253",

booktitle = "Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007",

note = "International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 ; Conference date: 19-04-2007 Through 23-04-2007",

}

Garnier, J, Dubuisson, P, Delnondedieu, M, Massoud, JP, Bréchet, Y, Leclercq, S, Besson, J, Scott, P, Averty, X & Rozenblum, F 2007, Deformation under irradiation of 304L and 316 austenitic stainless steels. in Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007, vol. 1, pp. 241-253, International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007, Whistler, British Columbia, Canada, 19/04/07.

Deformation under irradiation of 304L and 316 austenitic stainless steels. / Garnier, J.; Dubuisson, P.; Delnondedieu, M. et al.
Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 2007. p. 241-253 (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007; Vol. 1).

Research output: Chapter in Book/Report/Conference proceeding › Conference Paper › Other

TY - GEN

T1 - Deformation under irradiation of 304L and 316 austenitic stainless steels

AU - Garnier, J.

AU - Dubuisson, P.

AU - Delnondedieu, M.

AU - Massoud, J. P.

AU - Bréchet, Y.

AU - Leclercq, S.

AU - Besson, J.

AU - Scott, P.

AU - Averty, X.

AU - Rozenblum, F.

N1 - Conference code: 13th

PY - 2007

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AB - SA304L and CW316 stainless steels are the constitutive materials of the core internals of French Pressurized Water Reactors. In order to study the effects of irradiation on the austenitic stainless steels deformation, swelling mandrel tubes with different ceramics were irradiated in the core of OSIRIS reactor around 10dpa. Experiments have been carried out in PWR water and in inert NaK environment. A comprehensive experimental study of irradiation creep at 330°C for doses up to 120dpa and stresses between 127 and 200MPa is provided for both alloys. In order to assess stress and strain evolutions in the swelling mandrel tube, a constitutive law is proposed. This law is based on a large database of post irradiation mechanical tests and in pile creep tests on pressurized tubes performed on steels representative of French PWR internals. This provides a necessary step in a comprehensive study of behavior under simultaneous stress and irradiation.

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SN - 9781605600598

T3 - Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

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BT - Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

T2 - International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

Y2 - 19 April 2007 through 23 April 2007

ER -

Garnier J, Dubuisson P, Delnondedieu M, Massoud JP, Bréchet Y, Leclercq S et al. Deformation under irradiation of 304L and 316 austenitic stainless steels. In Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 2007. p. 241-253. (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007).

Deformation under irradiation of 304L and 316 austenitic stainless steels

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