The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment

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The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment. / van Walle, Eric; Chaouadi, Rachid; Gérard, Robert.

European Nuclear Society. Vol. ENC2016‐A0124 Poland : Studiecentrum voor Kernenergie, 2016. ENC2016‐A0124 (SCK•CEN Reports; No. ENC2016-A0124).

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

van Walle, E, Chaouadi, R & Gérard, R 2016, The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment. in European Nuclear Society. vol. ENC2016‐A0124, ENC2016‐A0124, SCK•CEN Reports, no. ENC2016-A0124, Studiecentrum voor Kernenergie, Poland, 2016 - ENC - European Nuclear Conference, Warsaw, Poland, 2016-10-09.

APA

van Walle, E., Chaouadi, R., & Gérard, R. (2016). The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment. In European Nuclear Society (Vol. ENC2016‐A0124). [ENC2016‐A0124] (SCK•CEN Reports; No. ENC2016-A0124). Poland: Studiecentrum voor Kernenergie.

Vancouver

van Walle E, Chaouadi R, Gérard R. The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment. In European Nuclear Society. Vol. ENC2016‐A0124. Poland: Studiecentrum voor Kernenergie. 2016. ENC2016‐A0124. (SCK•CEN Reports; ENC2016-A0124).

Author

van Walle, Eric ; Chaouadi, Rachid ; Gérard, Robert. / The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment. European Nuclear Society. Vol. ENC2016‐A0124 Poland : Studiecentrum voor Kernenergie, 2016. (SCK•CEN Reports; ENC2016-A0124).

Bibtex - Download

@inproceedings{586294a75c5344c69ccd786e934fd8bc,
title = "The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment",
abstract = "During the in-service inspection in the 2012 summer outage of the Doel-III reactor, a large number of quasi-laminar indications were detected. These ultrasonic observations were, after inspection of the Tihange-II vessel which is very similar to the Doel-III vessel, confirmed a few months later. Those unforeseen in-service inspection results have led to an extensive testing and evaluation program to which the Belgian Nuclear Research Centre (SCK•CEN) made a significant contribution with the determination of the materials properties, required for the safety integrity calculations. Four irradiation campaigns on a variety of materials relevant for the concerned case were successively carried out under well-controlled conditions in the BR2 Material Test Reactor. Given the high flux of the BR2 reactor, typically more than two orders of magnitude higher than on the vessel wall, the 40 years end-of-life fluence is reached in less than 4 weeks. Thanks to the extensive database developed through few decades of irradiation of a large number of structural materials, the outcome from the BR2 irradiation could be reliably transferred to the reactor pressure vessel. A number of issues were addressed with in-depth analysis to support the experimental data that were produced. This paper illustrates the key role of the BR2 reactor with several examples taken directly from the experiments performed within this project to demonstrate the applicability of accelerated data to the integrity of actual reactor pressure vessels.",
keywords = "BR2 reactor, structural integrity assessment, RPV embrittlement, Doel-III/Tihange-II reactor vessels, hydrogen flakes",
author = "{van Walle}, Eric and Rachid Chaouadi and Robert G{\'e}rard",
note = "Score=3",
year = "2016",
month = "10",
day = "10",
language = "English",
volume = "ENC2016‐A0124",
series = "SCK•CEN Reports",
publisher = "Studiecentrum voor Kernenergie",
number = "ENC2016-A0124",
booktitle = "European Nuclear Society",

}

RIS - Download

TY - GEN

T1 - The role of the BR2 material test reactor to determine the material properties of the flaked RPV shells in support of the structural integrity assessment

AU - van Walle, Eric

AU - Chaouadi, Rachid

AU - Gérard, Robert

N1 - Score=3

PY - 2016/10/10

Y1 - 2016/10/10

N2 - During the in-service inspection in the 2012 summer outage of the Doel-III reactor, a large number of quasi-laminar indications were detected. These ultrasonic observations were, after inspection of the Tihange-II vessel which is very similar to the Doel-III vessel, confirmed a few months later. Those unforeseen in-service inspection results have led to an extensive testing and evaluation program to which the Belgian Nuclear Research Centre (SCK•CEN) made a significant contribution with the determination of the materials properties, required for the safety integrity calculations. Four irradiation campaigns on a variety of materials relevant for the concerned case were successively carried out under well-controlled conditions in the BR2 Material Test Reactor. Given the high flux of the BR2 reactor, typically more than two orders of magnitude higher than on the vessel wall, the 40 years end-of-life fluence is reached in less than 4 weeks. Thanks to the extensive database developed through few decades of irradiation of a large number of structural materials, the outcome from the BR2 irradiation could be reliably transferred to the reactor pressure vessel. A number of issues were addressed with in-depth analysis to support the experimental data that were produced. This paper illustrates the key role of the BR2 reactor with several examples taken directly from the experiments performed within this project to demonstrate the applicability of accelerated data to the integrity of actual reactor pressure vessels.

AB - During the in-service inspection in the 2012 summer outage of the Doel-III reactor, a large number of quasi-laminar indications were detected. These ultrasonic observations were, after inspection of the Tihange-II vessel which is very similar to the Doel-III vessel, confirmed a few months later. Those unforeseen in-service inspection results have led to an extensive testing and evaluation program to which the Belgian Nuclear Research Centre (SCK•CEN) made a significant contribution with the determination of the materials properties, required for the safety integrity calculations. Four irradiation campaigns on a variety of materials relevant for the concerned case were successively carried out under well-controlled conditions in the BR2 Material Test Reactor. Given the high flux of the BR2 reactor, typically more than two orders of magnitude higher than on the vessel wall, the 40 years end-of-life fluence is reached in less than 4 weeks. Thanks to the extensive database developed through few decades of irradiation of a large number of structural materials, the outcome from the BR2 irradiation could be reliably transferred to the reactor pressure vessel. A number of issues were addressed with in-depth analysis to support the experimental data that were produced. This paper illustrates the key role of the BR2 reactor with several examples taken directly from the experiments performed within this project to demonstrate the applicability of accelerated data to the integrity of actual reactor pressure vessels.

KW - BR2 reactor

KW - structural integrity assessment

KW - RPV embrittlement

KW - Doel-III/Tihange-II reactor vessels

KW - hydrogen flakes

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/23802731

UR - https://www.euronuclear.org/events/enc/enc2016/transactions/ENC16-extended-abstracts.pdf

M3 - In-proceedings paper

VL - ENC2016‐A0124

T3 - SCK•CEN Reports

BT - European Nuclear Society

PB - Studiecentrum voor Kernenergie

CY - Poland

ER -

ID: 2422436