PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project

David Lidbury; Elisabeth Keim; Kim Wallin; Olivier Diard; Bernard Marini; Hans-Werner Viehrig; Stéphane Bugat

doi:10.1115/PVP2005-71558

PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project

David Lidbury, Elisabeth Keim, Kim Wallin, Olivier Diard, Bernard Marini, Hans-Werner Viehrig, Stéphane Bugat

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

3 Citations (Scopus)

Abstract

The EURATOM 6th Framework Integrated Project PERFECT (Prediction of Irradiation Damage Effects in Reactor Components) addresses irradiation damage in RPV materials and components by multi-scale modeling. This state-of-the-art approach offers many potential advantages over the conventional empirical methods used in current practice of nuclear plant lifetime management. Launched in January 2004, this 48-month project is focusing on two main components of nuclear power plants which are subject to irradiation damage: the ferritic steel reactor pressure vessel, and the austenitic steel internals. It is the purpose of the present paper to provide an overview of work being carried out in the RPV Mechanics Sub-project of PERFECT to predict the fracture behavior of PWR, BWR and WWER systems.

Original language	English
Title of host publication	ASME 2005 Pressure Vessel and Piping Conference
Publisher	American Society of Mechanical Engineers (ASME)
Pages	321-329
Volume	6
ISBN (Electronic)	0-7918-4191-X
DOIs	https://doi.org/10.1115/PVP2005-71558
Publication status	Published - 2005
MoE publication type	A4 Article in a conference publication
Event	ASME 2005 Pressure Vessels and Piping Conference - Denver, United States Duration: 17 Jul 2005 → 21 Jul 2005

Conference

Conference	ASME 2005 Pressure Vessels and Piping Conference
Country/Territory	United States
City	Denver
Period	17/07/05 → 21/07/05

Keywords

Multi-scale Modeling
Irradiation Damage
Discrete Dislocation Dynamics
Crystal Plasticity
RPV Components
Transgranular Cleavage
Brittle Intergranular Fracture
Master Curve
Crack-tip Constraint

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10.1115/PVP2005-71558

Cite this

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title = "PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project",

abstract = "The EURATOM 6th Framework Integrated Project PERFECT (Prediction of Irradiation Damage Effects in Reactor Components) addresses irradiation damage in RPV materials and components by multi-scale modeling. This state-of-the-art approach offers many potential advantages over the conventional empirical methods used in current practice of nuclear plant lifetime management. Launched in January 2004, this 48-month project is focusing on two main components of nuclear power plants which are subject to irradiation damage: the ferritic steel reactor pressure vessel, and the austenitic steel internals. It is the purpose of the present paper to provide an overview of work being carried out in the RPV Mechanics Sub-project of PERFECT to predict the fracture behavior of PWR, BWR and WWER systems.",

keywords = "Multi-scale Modeling, Irradiation Damage, Discrete Dislocation Dynamics, Crystal Plasticity, RPV Components, Transgranular Cleavage, Brittle Intergranular Fracture, Master Curve, Crack-tip Constraint",

author = "David Lidbury and Elisabeth Keim and Kim Wallin and Olivier Diard and Bernard Marini and Hans-Werner Viehrig and St{\'e}phane Bugat",

note = "Project code: G4SU00582; ASME 2005 Pressure Vessels and Piping Conference ; Conference date: 17-07-2005 Through 21-07-2005",

year = "2005",

doi = "10.1115/PVP2005-71558",

language = "English",

volume = "6",

pages = "321--329",

booktitle = "ASME 2005 Pressure Vessel and Piping Conference",

publisher = "American Society of Mechanical Engineers (ASME)",

address = "United States",

}

Lidbury, D, Keim, E, Wallin, K, Diard, O, Marini, B, Viehrig, H-W & Bugat, S 2005, PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project. in ASME 2005 Pressure Vessel and Piping Conference. vol. 6, American Society of Mechanical Engineers (ASME), pp. 321-329, ASME 2005 Pressure Vessels and Piping Conference, Denver, Colorado, United States, 17/07/05. https://doi.org/10.1115/PVP2005-71558

PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project. / Lidbury, David; Keim, Elisabeth; Wallin, Kim et al.
ASME 2005 Pressure Vessel and Piping Conference. Vol. 6 American Society of Mechanical Engineers (ASME), 2005. p. 321-329.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project

AU - Lidbury, David

AU - Keim, Elisabeth

AU - Wallin, Kim

AU - Diard, Olivier

AU - Marini, Bernard

AU - Viehrig, Hans-Werner

AU - Bugat, Stéphane

N1 - Project code: G4SU00582

PY - 2005

Y1 - 2005

N2 - The EURATOM 6th Framework Integrated Project PERFECT (Prediction of Irradiation Damage Effects in Reactor Components) addresses irradiation damage in RPV materials and components by multi-scale modeling. This state-of-the-art approach offers many potential advantages over the conventional empirical methods used in current practice of nuclear plant lifetime management. Launched in January 2004, this 48-month project is focusing on two main components of nuclear power plants which are subject to irradiation damage: the ferritic steel reactor pressure vessel, and the austenitic steel internals. It is the purpose of the present paper to provide an overview of work being carried out in the RPV Mechanics Sub-project of PERFECT to predict the fracture behavior of PWR, BWR and WWER systems.

AB - The EURATOM 6th Framework Integrated Project PERFECT (Prediction of Irradiation Damage Effects in Reactor Components) addresses irradiation damage in RPV materials and components by multi-scale modeling. This state-of-the-art approach offers many potential advantages over the conventional empirical methods used in current practice of nuclear plant lifetime management. Launched in January 2004, this 48-month project is focusing on two main components of nuclear power plants which are subject to irradiation damage: the ferritic steel reactor pressure vessel, and the austenitic steel internals. It is the purpose of the present paper to provide an overview of work being carried out in the RPV Mechanics Sub-project of PERFECT to predict the fracture behavior of PWR, BWR and WWER systems.

KW - Multi-scale Modeling

KW - Irradiation Damage

KW - Discrete Dislocation Dynamics

KW - Crystal Plasticity

KW - RPV Components

KW - Transgranular Cleavage

KW - Brittle Intergranular Fracture

KW - Master Curve

KW - Crack-tip Constraint

U2 - 10.1115/PVP2005-71558

DO - 10.1115/PVP2005-71558

M3 - Conference article in proceedings

VL - 6

SP - 321

EP - 329

BT - ASME 2005 Pressure Vessel and Piping Conference

PB - American Society of Mechanical Engineers (ASME)

T2 - ASME 2005 Pressure Vessels and Piping Conference

Y2 - 17 July 2005 through 21 July 2005

ER -

PERFECT - Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project

Abstract

Conference

Keywords

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