Chih-Cheng Chang

2025

Application of mini-flat and cylindrical test specimens to extract hardening law and ductility of neutron irradiated Eurofer97

Chang, C.-C., Terentyev, D., Bakaev, A., Zinovev, A., Del Serra, D., Verleysen, P. & Pardoen, T., Jul 2025, In: Fusion Engineering & Design. 216, 11 p., 115072.

Research output › peer-review

2024

Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage

Terentyev, D., Wirtz, M., Morgan, T. W., Nozawa, T., Zinovev, A., Chang, C.-C., Poleshchuk, K. & Elenbaas, J., Mar 2024, In: Fusion Engineering & Design. 200, 8 p., 114200.

Research output › peer-review

Open Access

Impact of neutron irradiation on the tensile properties of advanced EUROFER97-type steels

Kachko, O., Puype, A., Terentyev, D., Chang, C.-C., Rieth, M. & Petrov, R. H., Oct 2024, In: Journal of Nuclear Materials. 599, 12 p., 155176.

Research output › peer-review

2023

Defect evolution of neutron irradiated ITER grade tungsten after annealing

Papadakis, D., Mergia, K., Manios, E., Chatzikos, V., Spilios, D., Bonny, G., Van Renterghem, W., Terentyev, D., Chang, C.-C. & Messoloras, S., Apr 2023, In: Fusion Engineering & Design. 189, 8 p., 113486.

Research output › peer-review

Open Access

Development of sub-miniaturised testing methodology for W/Cu joints extracted from the ITER-specification monoblock

Poleshchuk, K., Terentyev, D., Chang, C.-C., Galatanu, A., Gavrilov, S., Zhou, H. & Verbeken, K., Sep 2023, In: Fusion Engineering & Design. 194, 8 p., 113925.

Research output › peer-review

Open Access

Effect of neutron irradiation to 0.7 and 1.4 dpa on the tensile mechanical properties and microstructure of EUROFER97 steel

Zinovev, A., Chang, C.-C., Eyken, J. V., Gaganidze, E. & Terentyev, D., May 2023, In: Science Talks. 6, 7 p., 100214.

Research output › peer-review

Effect of neutron irradiation to 0.7 dpa and 1.4 dpa on the tensile properties and fracture surface of EUROFER97 steel

Zinovev, A., Chang, C. C., Van Eyken, J., Gaganidze, E. & Terentyev, D., 15 Dec 2023, In: Journal of Nuclear Materials. 587, 11 p., 154742.

Research output › peer-review

Fusion-dedicated material irradiation facilities at MYRRHA: Conceptual design and damage equivalence studies

Terentyev, D., Leysen, W., Castin, N., Chang, C.-C., Kennedy, G., Stankovskiy, A. & Fiorito, L., Jun 2023, In: Fusion Engineering & Design. 191, 15 p., 113764.

Research output › peer-review

Open Access

Mechanical properties of structural metallic alloys for nuclear applications deduced by small punch test

Melkior, T., Terentyev, D., Chang, C.-C., Bakaev, A., Holmström, S., Lebediev, S. & Paputsia, A., Sep 2023, In: Journal of Nuclear Materials. 583, 33 p., 154521.

Research output › peer-review

On the equivalence of mini-flat and cylindrical tensile geometries to extract hardening law and ductility of Eurofer97

Chang, C.-C., Terentyev, D., Bakaev, A., Zinovev, A., Serra, D. D., Verleysen, P. & Pardoen, T., Sep 2023, In: fusion engineering and design. 194, 12 p., 113717.

Research output › peer-review

2022

Application of sub-miniaturized bending tests to extract tensile properties from neutron-irradiated metallic alloys

Bakaev, A., Terentyev, D., Zinovev, A., Chang, C.-C., Yin, C., Bakaev, V. A. & Zhurkin, E. E., Jan 2022, In: Journal of Nuclear Materials. 558, p. 1-19 19 p., 153320.

Research output › peer-review

Open Access

Development of irradiation tolerant tungsten alloys for high temperature nuclear applications

Terentyev, D., Jenus, P., Sal, E., Zinovev, A., Chang, C.-C., Garcia-Rosales, C., Kocen, M., Novak, S. & Van Renterghem, W., 27 Jun 2022, In: Nuclear Fusion. 62, 8, p. 1-17 17 p., 086035.

Research output › peer-review

Open Access

Effect of neutron irradiation on ductility of tungsten foils developed for tungsten-copper laminates

Zinovev, A., Terentyev, D., Chang, C.-C., Yin, C., Bakaev, A., Rieth, M., Lied, P., Reiser, J. & Bonnekoh, C., 10 Feb 2022, In: Nuclear Materials and Energy. 30, p. 1-10 10 p., 101133.

Research output › peer-review

Open Access

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High temperature nanoindentation of iron: experimental and computational study

Khvan, T., Noels, L., Terentyev, D., Dencker, F., Stauffer, D., Hangen, U. D., Van Renterghem, W., Chang, C.-C. & Zinovev, A., 24 May 2022, In: Journal of Nuclear Materials. 153815.

Research output › peer-review

Open Access

2021

Ductile to brittle transition temperature of advanced tungsten alloys for nuclear fusion applications deduced by miniaturized three-point bending tests

Yin, C., Terentyev, D., Zhang, T., Nogami, S., Antusch, S., Chang, C.-C., Petrov, R. & Pardoen, T., 1 Feb 2021, In: International Journal of Refractory Metals & Hard Materials. 95, p. 1-11 11 p., 105464.

Research output › peer-review

Open Access

Irradiation-induced hardening in fusion relevant tungsten grades with different initial microstructures

Chang, C.-C., Terentyev, D., Zinovev, A., Van Renterghem, W., Yin, C., Verleysen, P., Pardoen, T., Vilémová, M. & Matejicek, J., 7 Sep 2021, In: Physica Scripta. 96, p. 1-7 7 p., 124021.

Research output › peer-review

Open Access