Prediction of the in-reactor deformation of Zr-2.5wt%Nb pressure tubes using the crystal plasticity finite element method framework

Ahn, Dong-Hyun; Lee, Gyeong-Geun; Chun, Young-Bum; Jung, Jin-Woo

doi:10.1016/j.jnucmat.2022.153947

Cited by 4 publications

(3 citation statements)

References 24 publications

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“…Irradiation deformation models that have been developed for Zr-2.5Nb pressure tubing in CANDU reactors are either fully empirical [ 22 , 23 ] or semi-empirical in that there are some parameters that are derived from a mechanistic base [ 18 , 24 , 25 ]. Primary creep is empirically derived to best match available data, and it is assumed that there are three components to the steady-state creep rate, as outlined in Equation (2).…”

Section: Irradiation Creep In Nuclear Reactor Coresmentioning

confidence: 99%

Microstructural Effects on Irradiation Creep of Reactor Core Materials

Griffiths

2023

Materials

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The processes that control irradiation creep are dependent on the temperature and the rate of production of freely migrating point defects, affecting both the microstructure and the mechanisms of mass transport. Because of the experimental difficulties in studying irradiation creep, many different hypothetical models have been developed that either favour a dislocation slip or a mass transport mechanism. Irradiation creep mechanisms and models that are dependent on the microstructure, which are either fully or partially mechanistic in nature, are described and discussed in terms of their ability to account for the in-reactor creep behaviour of various nuclear reactor core materials. A rate theory model for creep of Zr-2.5Nb pressure tubing in CANDU reactors incorporating the as-fabricated microstructure has been developed that gives good agreement with measurements for tubes manufactured by different fabrication routes having very different microstructures. One can therefore conclude that for Zr-alloys at temperatures < 300 °C and stresses < 150 MPa, diffusional mass transport is the dominant creep mechanism. The most important microstructural parameter controlling irradiation creep for these conditions is the grain structure. Austenitic alloys follow similar microstructural dependencies as Zr-alloys, but up to higher temperature and stress ranges. The exception is that dislocation slip is dominant in austenitic alloys at temperatures < 100 °C because there are few barriers to dislocation slip at these low temperatures, which is linked to the enhanced recombination of irradiation-induced point defects.

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Section: Irradiation Creep In Nuclear Reactor Coresmentioning

confidence: 99%

Microstructural Effects on Irradiation Creep of Reactor Core Materials

Griffiths

2023

Materials

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“…The Zr-2.5 wt%Nb alloy is a typical pressure tube material in heavy water nuclear reactors [1][2][3] due to its excellent thermal conductivity and thermal stability, low thermal neutron absorption cross-section, and good creep behavior. [4][5][6][7] However, the performance deterioration of the Zr-2.5 wt% Nb alloy pressure tube under the effect of hydrogen isotopes 3,[8][9][10][11] (hydrogen embrittlement, hydrogen induced delayed cracking, etc.) is a critical concern in the nuclear industrial system.…”

Section: Introductionmentioning

confidence: 99%

Kinetics of hydrogen absorption/desorption in the Zr–2.5Nb alloy

Wang,

Cao

et al. 2024

Phys. Chem. Chem. Phys.

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“…At the same time, more energy-intensive and competitive nuclear setup of this type are being developed [ 1 , 2 , 3 ]. The most important structural elements of channel reactors are pressure pipes [ 4 , 5 , 6 , 7 ], the integrity of its the normal operation and safety of nuclear power plants determines. The design life of channel reactors is 30 years [ 6 ]; however, pressure pipes made of zirconium alloys operate less than the design period [ 7 , 8 , 9 ].…”

Section: Introductionmentioning

confidence: 99%

The Effect of Radial-Shear Rolling Deformation Processing on the Structure and Properties of Zr-2.5Nb Alloy

et al. 2023

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The rheological properties of the Zr-2.5Nb alloy by the strain rate range of 0.5–15 s−1 and by the temperature range of 20–770 °C was studied. The dilatometric method for phase states temperature ranges was experimentally determined. A material properties database for computer FEM simulation regards the indicated temperature-velocity ranges were created. Using this database and DEFORM-3D FEM-softpack, the radial shear rolling complex process numerical simulation was carried out. The contributed conditions for the ultrafine-grained state alloy structure refinement were determined. Based on the simulation results, a full-scale experiment of Zr-2.5Nb rod rolling a on a radial-shear rolling mill RSP-14/40 was carried out. It takes in seven passes from a diameter of 37–20 mm with a total diameter reduction ε = 85%. According to this case simulation data, the total equivalent strain in the most processed peripheral zone 27.5 mm/mm was reached. Due to the complex vortex metal flow, the equivalent strain over the section distribution was uneven with a gradient reducing towards the axial zone. This fact should have a deep effect on the structure change. Changes and structure gradient by sample section EBSD mapping with 2 mm resolution were studied. The microhardness section gradient by the HV 0.5 method was also studied. The axial and central zones of the sample by the TEM method were studied. The rod section structure has an expressed gradient from the formed equiaxed ultrafine-grained (UFG) structure on a few outer millimeters of the peripheral section to the elongated rolling texture in the center of the bar. The work shows the possibility of processing with the gradient structure obtaining and enhanced properties for the Zr-2.5Nb alloy, and a database for this alloy FEM numerical simulations are also presents.

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Prediction of the in-reactor deformation of Zr-2.5wt%Nb pressure tubes using the crystal plasticity finite element method framework

Cited by 4 publications

References 24 publications

Microstructural Effects on Irradiation Creep of Reactor Core Materials

Microstructural Effects on Irradiation Creep of Reactor Core Materials

Kinetics of hydrogen absorption/desorption in the Zr–2.5Nb alloy

The Effect of Radial-Shear Rolling Deformation Processing on the Structure and Properties of Zr-2.5Nb Alloy

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