1. Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay

    Yu, L. & Weetjens, E., 1 Jan 2016, SCK CEN. 40 p. (SCK•CEN Reports; no. ER-294)

    Research output: Report/bookER - External reportpeer-review

  2. A solution around a backfilled cavity in a low-permeability poroelastic medium with application in in situ heating tests

    Yu, L., Chen, G. & Weetjens, E., 14 Jun 2016, In: International Journal for Numerical and Analytical Methods in Geomechanics. 41, p. 3-29 26 p.

    Research output: Contribution to journalArticlepeer-review

  3. Experimental study on the hydro-mechanical behavior of Boom clay

    Yu, H-D., Chen, W-Z., Jia, S-P., Cao, J-J., Li, X. L. & Chen, G., Jul 2012, In: International Journal of Rock Mechanics & Mining Sciences. 53, p. 159-165

    Research output: Contribution to journalArticlepeer-review

  4. Creep behavior of boom clay

    Yu, H. D., Chen, W. Z., Gong, Z., Tan, X. J., Ma, Y. S., Li, X. L., Sillen, X. & Dizier, A., Jun 2015, In: International Journal of Rock Mechanics & Mining Sciences. 76, 06, p. 256-264

    Research output: Contribution to journalArticlepeer-review

  5. A Transversely Isotropic Damage Model for Boom Clay: Special Issue: Thermo-Hydro-Mechanical Effects in Clay Host Rocks for Radioactive Waste Repositories

    Yu, H. D., Chen, W. Z., Li, X. L., Sillen, X. & Dizier, A., Jan 2014, In: Rock Mechanics and Rock Engineering. 47, 1, p. 207-219

    Research output: Contribution to journalArticlepeer-review

  6. Seismic Isolation of Reactor Assembly for a Fixed Base - Accelerator Driven System Reactor Building

    Yoo, B. & De Bruyn, D., 1 Feb 2016, In: Journal of Civil Engineering and Architecture. 10, 2, p. 203-210 8 p.

    Research output: Contribution to journalArticlepeer-review

  7. Fiabilité aux radiations de composants optoélectroniques pour communication sans fil intra- satellite

    Yoann, D., Descas, Y. & Fernandez Fernandez, A., 6 Jul 2005, Bordeaux: Université de Bordeaux. 40 p.

    Research output: ThesisMaster's thesis

  8. A 1 MGy TID Radiation-Tolerant 56 mu W CMOS Temperature Sensor with +/- 1.7 degrees C accuracy

    Ying, C., Van Uffelen, M., Mont Casellas, L., Damiani, C., Ruiz Morales, E., Ranz Santana, R., Meek, R., Haist, B., De Cock, W., Vermeeren, L., Steyaert, M. & Leroux, P., Jan 2015, Proceedings of the 15th European Conference on Radiation and Its Effects on Components and Systems (RADECS) . Moskow: IEEE - Institute of Electrical and Electronics Engineers, p. 1-4 4 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  9. Ductile to brittle transition in ITER specification tungsten assessed by combined fracture toughness and bending tests analysis

    Yin, C., Terentyev, D., Pardoen, T., Petrov, R. & Zhenfeng, T., 10 Feb 2019, In: Materials Science and Engineering: A. 750, p. 20-30 11 p.

    Research output: Contribution to journalArticlepeer-review

  10. Tensile properties of baseline and advanced tungsten grades for fusion applications

    Yin, C., Terentyev, D., Pardoen, T., Bakaeva, A., Petrov, R., Antusch, S., Michael, R., Vilemova, M., Matejicek, J. & Zhang, T., 10 Apr 2018, In: International Journal of Refractory Metals & Hard Materials. 75, p. 153-162 10 p.

    Research output: Contribution to journalArticlepeer-review

  11. Impact of neutron irradiation on the strength and ductility of pure and ZrC reinforced tungsten grades

    Yin, C., Terentyev, D., Zhang, T., Petrov, R. & Pardoen, T., 15 Aug 2020, In: Journal of Nuclear Materials. 537, p. 1-15 15 p., 152226.

    Research output: Contribution to journalArticlepeer-review

  12. Anisotropy in the hardness of single crystal tungsten before and after neutron irradiation

    Yin, C., Bonny, G. & Terentyev, D., 1 Apr 2021, In: Journal of Nuclear Materials. 546, p. 1-7 7 p., 152759.

    Research output: Contribution to journalArticlepeer-review

  13. 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: Contribution to journalArticlepeer-review

  14. Assessment of mechanical properties of neutron irradiated tungsten and its alloys

    Yin, C. & Terentyev, D., 20 Nov 2020, UCL - Université Catholique de Louvain. 202 p.

    Research output: ThesisDoctoral thesis

  15. Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure

    Yin, C., Terentyev, D., Dubinko, A., Zhang, T., Wirtz, M., Antusch, S., Petrov, R. & Pardoen, T., 29 Apr 2021, In: Nuclear Fusion. 61, p. 1-11 11 p., 066012.

    Research output: Contribution to journalArticlepeer-review

  16. 520-d Isolation and confinement simulating a flight to Mars reveals heightened immune responses and alterations of leukocyte phenotype

    Yi, B., Rykova, M., Feuerecker, M., Jäger, B., Ladinig, C., Basner, M., Hörl, M., Matzel, S., Kaufmann, I., Strewe, C., Nichiporuk, I., Vassilieva, G., Rinas, K., Baatout, S., Schelling, G., Thiel, G., Dinges, D. F., Morukov, B. & Choukèr, A., 2 Apr 2015, In: Brain, Behavior, and Immunity. 40, p. 203-210

    Research output: Contribution to journalArticlepeer-review

  17. Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

    Ye, B., Bhattacharya, S., Mo, K., Yun, D., Pellin, M., Fortner, J., Hofmann, G., Yacout, A. M., Wiencek, T., Leenaers, A. & Van den Berghe, S., 6 May 2015, In: Journal of Nuclear Materials. 464, p. 236-244 8 p.

    Research output: Contribution to journalArticlepeer-review

  18. A modelling study of the inter-diffusion layer formation in U-Mo/Al dispersion fuel plates at high power

    Ye, B., Hofmann, G. L., Leenaers, A., Bergeron, A., Kuzminov, V., Van den Berghe, S. & Kim, Y. S., 1 Feb 2018, In: Journal of Nuclear Materials. 499, p. 191-203 13 p.

    Research output: Contribution to journalArticlepeer-review

  19. 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

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