Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials

Research output: Contribution to journalArticlepeer-review

Standard

Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials. / Lucon, Enrico; Scibetta, Marc; Chaouadi, Rachid; van Walle, Eric; Gérard, Robert.

In: International Journal of Pressure Vessels and Piping, Vol. 84, No. 9, 19.09.2007, p. 536-544.

Research output: Contribution to journalArticlepeer-review

Bibtex - Download

@article{7bfb6366354e45a79647964902424abe,
title = "Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials",
abstract = "In the context of existing regulatory codes, the integrity assessment of the pressure vessel of a nuclear power plant (NPP) is based on the empirical assumption that the fracture toughness of the surveillance materials, expressed in terms of a lower bound curve indexed by a reference temperature RTNDT, undergoes a shift under irradiation by an amount equal to the increment of the T41 J index temperature measured from surveillance Charpy tests. Nowadays, an alternative route exists, based on: reconstitution of previously tested specimens; execution of fracture toughness tests in the irradiated condition; Master Curve analysis of the results obtained and finally determination of an alternative toughness-based reference temperature {\dh}RTT0 {\TH}, which can be used to index the lower bound KIc curve. As we demonstrate in this paper for several surveillance materials extracted from Belgian power plants, this {\textquoteleft}{\textquoteleft}advanced{\textquoteright}{\textquoteright} approach can provide NPP owners and plant engineers an additional safety margin with respect to the operating limits of the reactor and the pressurized thermal shock (PTS) screening criteria. These additional safety margins have been found particularly significant for older plants, for which the actual fracture toughness in the unirradiated condition is often underestimated by the approach based on RTNDT.",
keywords = "Fracture toughness, Reactor pressure vessel, Reference temperature, Reconstitution, Master Curve, PTS screening criteria",
author = "Enrico Lucon and Marc Scibetta and Rachid Chaouadi and {van Walle}, Eric and Robert G{\'e}rard",
note = "Score = 10",
year = "2007",
month = sep,
day = "19",
doi = "10.1016/j.ijpvp.2007.05.001",
language = "English",
volume = "84",
pages = "536--544",
journal = "International Journal of Pressure Vessels and Piping",
issn = "0308-0161",
publisher = "Elsevier",
number = "9",

}

RIS - Download

TY - JOUR

T1 - Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials

AU - Lucon, Enrico

AU - Scibetta, Marc

AU - Chaouadi, Rachid

AU - van Walle, Eric

AU - Gérard, Robert

N1 - Score = 10

PY - 2007/9/19

Y1 - 2007/9/19

N2 - In the context of existing regulatory codes, the integrity assessment of the pressure vessel of a nuclear power plant (NPP) is based on the empirical assumption that the fracture toughness of the surveillance materials, expressed in terms of a lower bound curve indexed by a reference temperature RTNDT, undergoes a shift under irradiation by an amount equal to the increment of the T41 J index temperature measured from surveillance Charpy tests. Nowadays, an alternative route exists, based on: reconstitution of previously tested specimens; execution of fracture toughness tests in the irradiated condition; Master Curve analysis of the results obtained and finally determination of an alternative toughness-based reference temperature ðRTT0 Þ, which can be used to index the lower bound KIc curve. As we demonstrate in this paper for several surveillance materials extracted from Belgian power plants, this ‘‘advanced’’ approach can provide NPP owners and plant engineers an additional safety margin with respect to the operating limits of the reactor and the pressurized thermal shock (PTS) screening criteria. These additional safety margins have been found particularly significant for older plants, for which the actual fracture toughness in the unirradiated condition is often underestimated by the approach based on RTNDT.

AB - In the context of existing regulatory codes, the integrity assessment of the pressure vessel of a nuclear power plant (NPP) is based on the empirical assumption that the fracture toughness of the surveillance materials, expressed in terms of a lower bound curve indexed by a reference temperature RTNDT, undergoes a shift under irradiation by an amount equal to the increment of the T41 J index temperature measured from surveillance Charpy tests. Nowadays, an alternative route exists, based on: reconstitution of previously tested specimens; execution of fracture toughness tests in the irradiated condition; Master Curve analysis of the results obtained and finally determination of an alternative toughness-based reference temperature ðRTT0 Þ, which can be used to index the lower bound KIc curve. As we demonstrate in this paper for several surveillance materials extracted from Belgian power plants, this ‘‘advanced’’ approach can provide NPP owners and plant engineers an additional safety margin with respect to the operating limits of the reactor and the pressurized thermal shock (PTS) screening criteria. These additional safety margins have been found particularly significant for older plants, for which the actual fracture toughness in the unirradiated condition is often underestimated by the approach based on RTNDT.

KW - Fracture toughness

KW - Reactor pressure vessel

KW - Reference temperature

KW - Reconstitution

KW - Master Curve

KW - PTS screening criteria

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_82961

UR - http://knowledgecentre.sckcen.be/so2/bibref/4433

U2 - 10.1016/j.ijpvp.2007.05.001

DO - 10.1016/j.ijpvp.2007.05.001

M3 - Article

VL - 84

SP - 536

EP - 544

JO - International Journal of Pressure Vessels and Piping

JF - International Journal of Pressure Vessels and Piping

SN - 0308-0161

IS - 9

ER -

ID: 164276