Crystal Plasticity Modelling of Neutron Irradiation Effects on the Flow and Damage Behaviour of Zircaloy-4

Jose, Nevil Martin; Samal, M. K.; Durgaprasad, P.V.; Alankar, Alankar; Dutta, B.K.

doi:10.1007/978-981-16-8724-2_23

Cited by 1 publication

(2 citation statements)

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“…Accounting for the presence of irradiation-induced dislocation loops (leading to irradiation hardening) and their annihilation due to gliding dislocations (leading to softening) made it possible to reproduce the macroscopic stressstrain response of the material. Additionally, Jose et al [61] used CPFEM to study neutronirradiated Zircaloy-4. In addition to accounting for the presence of irradiation-induced defects and their annihilation, a model of damage by void growth was introduced.…”

Section: Materials For Fuel Claddingmentioning

confidence: 99%

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Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

Frydrych

2023

Crystals

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The review starts by highlighting the significance of nuclear power plants in the contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions. Then, it describes the impact of irradiation on the microstructure and mechanical properties of reactor structural materials. The main part provides the reader with a thorough overview of crystal plasticity models developed to address the irradiation effects so far. All three groups of the most important materials are included. Namely, the Zr alloys used for fuel cladding, austenitic stainless steels used for reactor internals, and ferritic steels used for reactor pressure vessels. Other materials, especially those considered for construction of future fission and fusion nuclear power plants, are also mentioned. The review also pays special attention to ion implantation and instrumented nanoindentation which are common ways to substitute costly and time-consuming neutron irradiation campaigns.

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Section: Materials For Fuel Claddingmentioning

confidence: 99%

“…In addition to accounting for the presence of irradiation-induced defects and their annihilation, a model of damage by void growth was introduced. Contrary to other models for Zr, both [60,61] applied a thermal activation flow rule (cf. Equation ( 4)) in their studies.…”

Section: Materials For Fuel Claddingmentioning

confidence: 99%

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

Frydrych

2023

Crystals

View full text Add to dashboard Cite

show abstract

Crystal Plasticity Modelling of Neutron Irradiation Effects on the Flow and Damage Behaviour of Zircaloy-4

Cited by 1 publication

References 20 publications

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

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