A spatially-resolved model of neutron-irradiated tungsten coupling stochastic cluster dynamics and finite deformation plasticity

Chatterjee, Sabyasachi; Yu, Qianran; Li, Yang; Roche, Kenneth; Marian, Jaime; Po, Giacomo

doi:10.1016/j.jnucmat.2024.155526

A spatially-resolved model of neutron-irradiated tungsten coupling stochastic cluster dynamics and finite deformation plasticity

Journal Article · Mon Nov 18 23:00:00 EST 2024 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2024.155526· OSTI ID:2560683

^[1]; Yu, Qianran ^[2]; Li, Yang ^[3]; Roche, Kenneth ^[4]; ^[5]; Po, Giacomo ^[6]

Indian Inst. of Technology (IIT), New Delhi (India); Univ. of Miami, FL (United States)
Clemson Univ., SC (United States)
Shanghai University (China)
Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Univ. of California, Los Angeles, CA (United States)
Univ. of Miami, FL (United States)

Structural materials used in nuclear reactors face severe degradation in mechanical properties, such as hardening and embrittlement. At the microscopic scale, this occurs due to creation and accumulation of irradiation-induced defects and their interaction with system dislocations. Although techniques exist which can model evolution of irradiation defects, for instance kinetic transport theory-based models, their interaction with mechanical deformation of the bulk material has not been investigated extensively. In this work, we demonstrate a novel spatially-resolved multiscale coupling between microscopic irradiation defect evolution, modeled using Stochastic Cluster Dynamics (SCD) and macroscopic mechanical deformation modeled using a finite-deformation plasticity model. SCD is used to determine the statistically averaged defect cluster spacing, dependent on operating conditions such as irradiation dose and temperature. This acts as an initial condition that governs the critical resolved shear stress of dislocation glide in the macroscopic plasticity model. This framework is used to predict mechanical behavior in post-mortem test of irradiated Tungsten samples, which has found its importance as structural material used in nuclear reactors. The results obtained using the coupled approach are in good agreement with experimental data of uniaxial tension tests. The model is able to capture the effect of temperature and irradiation dose on the material hardening. Two methods are proposed to estimate hardness – using Tabor's Law relating uniaxial yield stress to hardness and from flat-punch simulations. The results are in reasonable agreement with hardness data from micro-indentation experiments of irradiated Tungsten samples. Finally, the model is also able to reveal microstructural details such as spatial variation in defect density and local stress.

View Accepted Manuscript (DOE)

Research Organization:: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-76RL01830; SC0019157

OSTI ID:: 2560683

Report Number(s):: PNNL-SA--194536

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 605; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
computational modeling
finite deformation plasticity
irradiation hardening
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stochastic cluster dynamics

A spatially-resolved model of neutron-irradiated tungsten coupling stochastic cluster dynamics and finite deformation plasticity

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