Nuclear Materials Science

Organisational unit: Institute

  1. Article › Research
  2. TEM investigation of neutron irradiated and post irradiation annealed tungsten materials

    Van Renterghem, W., Bonny, G. & Terentyev, D., 19 May 2022, In: Fusion Engineering & Design. 180, p. 1-13 13 p., 113170.

    Research output: Contribution to journalArticlepeer-review

  3. TEM investigation of SCC crack tips in high Si stainless steel tapered specimens

    Penders, A., Konstantinovic, M., Van Renterghem, W., Bosch, R-W. & Schryvers, D., 14 Feb 2021, In: Corrosion Engineering, Science and Technology. 56, 8, p. 767-777 12 p.

    Research output: Contribution to journalArticlepeer-review

  4. TEM investigation of the effect of He-seeding on plasma induced defects in tungsten

    Van Renterghem, W., Dubinko, A., Bakaeva, A. & Terentyev, D., 16 May 2018, In: Journal of Nuclear Materials. 508, p. 74-81 7 p.

    Research output: Contribution to journalArticlepeer-review

  5. TEM Observation of Loops Decorating Dislocations and Resulting Source Hardening of Neutron-Irradiated Fe-Cr Alloys

    Bergner, F., Hernández-Mayoral, M., Heintze, C., Konstantinovic, M., Malerba, L. & Pareige, C., 18 Jan 2020, In: Metals. 10, 1, p. 1-10 10 p., 147.

    Research output: Contribution to journalArticlepeer-review

  6. Temperature and deformation effect on the low and high angle grain boundary structure of a double forged pure tungsten

    Sheng, H., Sun, Z., Uytdenhouwen, I., Van Oost, G., Vleugels, J. & Konstantinovic, M., 21 Jan 2015, In: International Journal of Refractory Metals & Hard Materials. 50, 5, p. 184-190

    Research output: Contribution to journalArticlepeer-review

  7. Temperature dependence of irradiation hardening due to dislocation loops and precipitates in RPV steels andd model alloys

    Terentyev, D., Kotrechko, S., Dubinko, V., Stetsenko, N., He, X. & Sorokin, M. V., 12 Apr 2015, In: Journal of Nuclear Materials. 464, p. 6-15 10 p.

    Research output: Contribution to journalArticlepeer-review

  8. Temperature dependence of liquid metal embrittlement susceptibility of a modified 9Cr-1Mo steel under low cycle fatigue in lead-bismuth eutectic at 160-450°C

    Gong, X., Marmy, P., Qin, L. & Verlinden, B., 14 Jun 2015, In: Journal of Nuclear Materials. 468, p. 289-298 10 p.

    Research output: Contribution to journalArticlepeer-review

  9. Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation

    Ye, B., Miao, Y., Shi, J., Salvato, D., Mo, K., Jamison, L., Bergeron, A., Hofmann, G. L., Leenaers, A., Oaks, A., Yacout, A. M., Van den Berghe, S., Petry, W. & Kim, Y. S., 1 Feb 2021, In: Journal of Nuclear Materials. 544, p. 1-14 14 p., 152684.

    Research output: Contribution to journalArticlepeer-review

  10. Tensile fracture behavior of notched 9Cr-1Mo ferritic-martensitic steel specimens in contact with liquid lead-bismuth eutectic at 350 °C

    Gong, X., Stergar, E., Marmy, P. & Gavrilov, S., 24 Apr 2017, In: Materials Science and Engineering: A. 692, p. 139-145

    Research output: Contribution to journalArticlepeer-review

  11. Tensile properties and internal friction study of dislocation movement in iron–copper system as a function of copper precipitation

    Konstantinovic, M., Al Mazouzi, A., Scibetta, M., van Walle, E. & Van Dyck, S., Feb 2007, In: Journal of Nuclear Materials. 362, 2-3, p. 283-286

    Research output: Contribution to journalArticlepeer-review

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