Endommagement des alliages métalliques par les neutrons rapides

Boutard, Jean-Louis

doi:10.1051/refdp/201438017

Cited by 2 publications

(2 citation statements)

References 11 publications

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“…Using a tensile stress at σm=1200 MPa could seem large compared to the value measured on Pd hydride/deuteride (σm < 300 MPa (16,23)). However, it was demonstrated that 3 He bubbles embrittle significantly the matrix and consequently increase tensile stress value (24). As shown in Figure 4, both models succeed in replicating the Pd tritide swelling measured by pycnometry and tomography.…”

Section: Inputmentioning

confidence: 57%

Aging of Pd under tritium: Influence of 3He generation and associated mechanisms

Evin

Segard

Leroy

et al. 2023

Journal of Alloys and Compounds

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Section: Inputmentioning

confidence: 57%

Aging of Pd under tritium: Influence of 3He generation and associated mechanisms

Evin

Segard

Leroy

et al. 2023

Journal of Alloys and Compounds

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“…This phenomenon is quantified in displacement per atoms (dpa). This means that for a material receiving a dose of 100 dpa, each atom moves 100 times [34]. During the initial collision between neutron and atom (PKA), nuclear transmutation reactions occur.…”

Section: Future Perspectivesmentioning

confidence: 99%

Development of a thermo-mechanical behaviour model adapted to the ITER vacuum vessel material

Sabourin

Désoyer

Lejeunes

et al. 2021

Fusion Engineering and Design

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The ITER machine has been classified as a Basic Nuclear Installation French nuclear regulator (INB n°174), which implies that it will be the first fusion reactor to go through complete French nuclear licencing. The combination of mechanic and electromagnetic phenomena with the heat loads caused by neutron streaming requires a multi-physics approach to the damage assessment, which has not yet been implemented in the common nuclear codes and standards.The general damage prevention methodology consists in guaranteeing the structural integrity of a component. The development of design rules has mainly two origins: prevention of damage from monotonic mechanical loads and prevention of damage from repeated application of loads. In most cases, structural integrity is justified within a linear elastic behaviour but when this route is not enough to respect the design criteria, several non-linear approaches to the material's mechanical behaviour can be considered, requiring more elaborated demonstration of the design compliance. Nevertheless, the models proposed in the nuclear model database are sometimes not sufficient to properly describe the experimentally observed cyclic plasticity behaviour and, in particular, the ratcheting and shakedown phenomena.According to ITER community experts in materials and analyses, a thermo-mechanical behaviour model fitting the ITER Tokamak materials data will guarantee the best prediction of the damage considering a nuclear and a multi-physic loading condition.This paper describes the assessment of the non-linear behaviour of Vacuum Vessel (VV) material with a strong thermomechanical coupling and a damage parameter to prevent crack initiation. More precisely, Chaboche's models available in the literature (elasto-(visco)-plasticity models, with various types of hardening) have been enriched in order to explicitly take into account the influence of the temperature on the mechanical behaviour and, reciprocally, the influence of the mechanical behaviour on the temperature. Mechanical cycling tests have been performed on the VV constitutive material, emphasizing on the progressive deformation state up to failure mode, i.e., ratcheting. The proposed models have been tested on a homogeneous problem and the results compared with uniaxial test results; this type of simulation is commonly called "0D"analysis. The last part of this document describes the finite element implementation of the constitutive material model and its application to the ITER VV welded support.

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Endommagement des alliages métalliques par les neutrons rapides

Cited by 2 publications

References 11 publications

Aging of Pd under tritium: Influence of 3He generation and associated mechanisms

Aging of Pd under tritium: Influence of 3He generation and associated mechanisms

Development of a thermo-mechanical behaviour model adapted to the ITER vacuum vessel material

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