Collaborations and top research areas from the last five years
Recent external collaboration on country/territory level. Dive into details by clicking on the dots or
Research output
- 6 Article
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Investigation of neutron irradiated W/CuCrZr joints
Poleshchuk, K., Terentyev, D., Galatanu, A. & Verbeken, K., Jan 2025, In: Journal of Nuclear Materials. 604, 9 p., 155496.Research output › peer-review
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Strength of a circumferential W/Cu/CuCrZr joint of ITER monoblock
Poleshchuk, K., Terentyev, D., Crea, F., Gavila, P., Roccella, S. & Verbeken, K., Jun 2025, In: Nuclear Materials and Energy. 43, 11 p., 101947.Research output › peer-review
Open Access -
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 -
Low cycle fatigue of EUROFER97 investigated for test blanket modules of ITER: An interlaboratory study
Zinovev, A., Lamagnère, P., Poleshchuk, K., Terentyev, D., Bernardi, D., Cristalli, C., Leon-Gutierrez, E., García-Rodríguez, N., Caes, C., Pintsuk, G. & Aiello, G., Aug 2024, In: Journal of Nuclear Materials. 597, 10 p., 155127.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