Warm PreStress effect on highly irradiated reactor pressure vessel steel

Hure, Jérémy; Vaille, C.; Wident, P.; Moinereau, Dominique; Landron, Caroline; Chapuliot, S.; Benhamou, Claude Laurent; Tanguy, B.

doi:10.1016/j.jnucmat.2015.04.046

Cited by 10 publications

(14 citation statements)

References 30 publications

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“…It has been irradiated in the Material Testing Reactors Osiris (CEA Saclay) and RBT-6 (RIAR) to different fast neutron fluences. Experimental characterization and modelling on Material #2 have been reported in previous studies [42,45]. The irradiation conditions are summarized in Tab.…”

Section: Methodsmentioning

confidence: 99%

“…Typically, tensile tests on notched samples or torsion tests allow assessing large strains [41] and are widely used for unirradiated material. Experimental data remains however scarce for irradiated RPV steels [42], especially regarding the effect of irradiation level. Secondly, fracture models, either brittle or ductile, have parameters requiring calibration.…”

Section: Introductionmentioning

confidence: 99%

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Numerical prediction of the effect of irradiation on the Charpy Upper Shelf Energy of Reactor Pressure Vessel steels

Hure

Parrot

Meunier

2022

Journal of Nuclear Materials

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Numerical prediction of the effect of irradiation on the Charpy Upper Shelf Energy of Reactor Pressure Vessel steels

Hure

Parrot

Meunier

2022

Journal of Nuclear Materials

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“… typical RPV steels: 16MND5 (~ A508 Cl3), 18MND5 (~ A533B)  thermal aged steels for simulation of irradiation embrittlement (17MoV8.4 mod.)  un-irradiated and irradiated RPV steels (16MND5), including highly irradiated materials (3.5 10 19 n/cm 2 < fluence  < ~ 1.4 10 20 n/cm 2 ), coming both from EDF Irradiation Surveillance Program (PSI) and Materials Testing Reactors (MTR)  uniaxial or biaxial loading with mechanical or thermal loading  fracture mechanics specimens (CT, SENB, CTpor …)  medium or large scale specimens (cylinder, PTS-D disks, cruciform specimens, bend bars ..)  WPS type loading path ( Figure 3 [10]). Based on these experiments, the beneficial effect of WPS regarding the brittle fracture resistance of RPV steels is fully confirmed, whatever the experimental conditions (e.g.…”

Section: Experimental Validation Of Warm Pre-stress On Rpv Steelsmentioning

confidence: 99%

Inclusion of Warm Pre-Stress Concept in French RPV Structural Integrity Assessment

Moinereau

Ait-Bachir

Chapuliot

et al. 2016

Volume 7: Operations, Applications and Components

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Evaluation of the fracture resistance of nuclear reactor pressure vessel (RPV) regarding the risk of brittle fracture is a key point in the structural integrity assessment of the component (RPV). Such approach is codified in French RSE-M code, based on a very conservative methodology. With respect to long term operation, an improvement of the present methodology is necessary and in progress to reduce this conservatism. One possible significant improvement is the inclusion of the warm pre-stress (WPS) concept in the assessment. After a short description of the WPS concept, the process engaged in France to allow inclusion of WPS in the integrity assessment is presented. In a first step, experimental and numerical studies have been conducted in France by EDF, CEA and AREVA (also including international collaborations and projects) to demonstrate and validate the beneficial effect of WPS on the brittle fracture resistance of RPV steels. A large panel of experimental results and data is now available obtained on small, medium and large scale specimens on representative RPV steels (including highly irradiated RPV materials). These data have been included in a specific WPS experimental database. Main experiments have been interpreted by refined computations, based on elastic plastic analyses and local approach to cleavage fracture. In a second step, a new criterion (ACE criterion) has been proposed by French organizations (AREVA, CEA and EDF) for an easy simplified evaluation of warm pre-stress effect on the brittle fracture resistance of RPV steels. Accuracy and conservatism of the criterion is verified by comparison to experimental data results and numerical analyses. Finally, implementation of the WPS effect in the French RSE-M code (for in service assessment) is in progress, based on the ACE criterion. The present paper summarizes all these steps leading to codification of WPS in RSE-M code.

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“…This has also been identified by Bordet et al [6] conducting very similar transient load experiments as featured in this study. The WPS-effect through transient load paths was also successfully investigated by Jacquemoud et al [15], Hure et al [13], Smith and Garwood [28], or Moinereau et al [18], proving its relevance and impact on the assessment of fracture toughness for different types of ferritic-bainitic reactor pressure vessel steels. Of special interest regarding this study are results from [15], which emphasizes on proving that active plasticity, the ongoing plastic deformation of the ferric matrix, is a necessary condition for cleavage fracture.…”

Section: Introductionmentioning

confidence: 99%

Cleavage fracture assessment of transient thermo-mechanical loading situations by local approach

Tlatlik

Siegele

2017

Engineering Fracture Mechanics

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Warm PreStress effect on highly irradiated reactor pressure vessel steel

Cited by 10 publications

References 30 publications

Numerical prediction of the effect of irradiation on the Charpy Upper Shelf Energy of Reactor Pressure Vessel steels

Numerical prediction of the effect of irradiation on the Charpy Upper Shelf Energy of Reactor Pressure Vessel steels

Inclusion of Warm Pre-Stress Concept in French RPV Structural Integrity Assessment

Cleavage fracture assessment of transient thermo-mechanical loading situations by local approach

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