au.\*:("DE VRIES, M. I")
Results 1 to 7 of 7
Selection :
Fatigue and crack growth properties of type 316 steel for fusion applications = Fatigue et propriétés de croissance des fissures dans un acier de type 316 pour des applications de fusionVAN DER SCHAAF, B; DE VRIES, M. I.Radiation effects. 1987, Vol 101, Num 1-4, pp 173-187, issn 0033-7579Conference Paper
Irradiation hardening of V-4Cr-4TiVAN OSCH, E. V; DE VRIES, M. I.Journal of nuclear materials. 1999, Vol 271-72, pp 162-166, issn 0022-3115Conference Paper
Irradiation testing of 316l(N)-IG austenitic stainless steel for ITERVAN OSCH, E. V; HORSTEN, M. G; DE VRIES, M. I et al.Journal of nuclear materials. 1998, Vol 258263, pp 301-307, issn 0022-3115, aConference Paper
LYRA and other projects on RPV steel embrittlement : Study and mitigation of the AMES NetworkDEBARBERIS, L; VON ESTORFF, U; CRUTZEN, S et al.Nuclear engineering and design. 2000, Vol 195, Num 2, pp 217-226, issn 0029-5493Conference Paper
Irradiation devices and testing facilities for small specimens of low-activation steelsTARTAGLIA, G. P; DE VRIES, M. I; HORSTEN, M. G et al.Journal of nuclear materials. 1994, Vol 212-15, Num B, pp 1655-1660, issn 0022-3115Conference Paper
Tensile properties of type 316L(N) stainless steel irradiated to 10 displacements per atomHORSTEN, M. G; DE VRIES, M. I.Journal of nuclear materials. 1994, Vol 212-15, Num A, pp 514-518, issn 0022-3115Conference Paper
Materials properties of irradiated austenitic stainless steel for LWR internal applicationsHORSTEN, M. G; VAN-OSCH, E. V; DE-VRIES, M. I et al.Fontevraud. Colloque international. 1998, pp 307-317, 2VolConference Paper