An Integrated Approach to Fusion Material Research at SCK·CEN

REFERENCES

• R.L. KLUEH et al., “Ferritic/Martensitic Steels – Overview of Recent Results”, Journal of Nuclear Materials, 307-311, 455 (2002).
   Web of Science ®Google Scholar
• M. GASPAROTTO et al., “Survey of In-Vessel Candidate Materials for Fusion Power Plants -The European Materials R&D Programme”, Fusion Engineering and Design, 66-68, 129 (2003).
   Web of Science ®Google Scholar
• B. VAN DER SCHAAF et al., “The Development of EUROFER Reduced Activation Steel”, Fusion Engineering and Design, 69, 197 (2003).
   Web of Science ®Google Scholar
• E. LUCON, “Mechanical Properties of the European Reference RAFM Steel (EUROFER97) Before and After Irradiation at 300 °C (0.3-2 dpa)”, SCK•CEN Report BLG-962, November 2003.
   Google Scholar
• K. SHIBA, and A. HISHINUMA, “Low-Temperature Irradiation Effects on Tensile and Charpy Properties of Low-Activation Ferritic Steels”, Journal of Nuclear Materials, 283-287, 474 (2000).
   Web of Science ®Google Scholar
• J. RENSMAN et al., “Irradiation resistance of EUROFER97 at 300 °C up to 10 dpa”, Journal of Nuclear Materials, 329-333, Part 2, 1113 (2004).
   Web of Science ®Google Scholar
• S. JITSUKAWA et al., “Development of an Extensive Database of Mechanical and Physical Properties for Reduced-Activation Martensitic Steel F82H”, Journal of Nuclear Materials, 307, 186 (2002).
   Web of Science ®Google Scholar
• J. RENSMAN et al., “Tensile Properties and Transition Behaviour of RAFM Steel Plate and Welds Irradiated upto 10 dpa at 300 °C”, Journal of Nuclear Materials, 307-311, 245 (2002).
   Web of Science ®Google Scholar
• R. LINDAU et al., “Mechanical and Microstructural Properties of a Hipped RAFM ODS-Steel”, Journal of Nuclear Materials, 307-311, 769 (2002).
   Web of Science ®Google Scholar
• S. VAN DYCK, and R.W. BOSCH, “Stress Corrosion Susceptibility of Ferritic-Martensitic Stainless Steels for Fusion Applications in High Temperature Water”, Proceedings of EUROCORR2001, Riva del Garda (Italy), Sep 30–Oct 4, 2001.
   Google Scholar
• M. VANKEERBERGHEN, R.W. BOSCH, and R. VAN NIEUWENHOVEN, “In-pile Electrochemical Measurements on AISI 316 L(N) IG and EUROFER 97 - I: Experimental Results”, Journal of Nuclear Materials, 312, 191 (2003).
   Web of Science ®Google Scholar
• G. S. WAS, “Recent Developments in Understanding Irradiation Assisted Stress Corrosion Cracking”, Proceedings of the 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, Aug. 10–14, 2003, ANS, 965.
   Google Scholar
• T. SAMPLE, and H. KOLBE, “Liquid Metal Embrittlement (LME) Susceptibility of the 8±9% Cr Martensitic Steels F82H-mod., OPTIFER IVb and their Simulated Welded Structures in Liquid Pb±17Li”, Journal of Nuclear Materials, 283-287, 1336 (2000).
   Web of Science ®Google Scholar
• S. VAN DYCK, “The Installation of an IASCC Autoclave Test System at the SCK-CEN Hot Laboratory”, Proceedings of the International Workshop on Hot Laboratories & Remote Handling, Madrid (Spain), Oct 2001.
   Google Scholar
• C. F. OLD, “Liquid Metal Embrittlement of Nuclear Materials”, Journal of Nuclear Materials, 92, 2 (1980).
   Web of Science ®Google Scholar
• A. KOHYAMA et al., “Low-Activation Ferritic and Martensitic Steels for Fusion Application” Journal of Nuclear Materials, 233-237, 138 (1996).
   Web of Science ®Google Scholar
• E. DAUM et al., “The International Fusion Materials Irradiation Facility IFMIF — An Overview of User Aspects”, Fusion Engineering and Design, 49-50, 435 (2000).
   Web of Science ®Google Scholar
• G.R. ODETTE et al., “Multiscale-Multiphysics Modeling of Radiation-Damaged Materials: Embrittlement of Pressure-Vessel Steels”, MRS Bulletin 26(3), 176 (March 2001).
   Web of Science ®Google Scholar
• B.D. WIRTH et al., “Mechanical Property Degradation in Irradiated Materials: A Multiscale Modeling Approach”, Nucl. Instr. & Meth. B 180, 23 (2001).
   Web of Science ®Google Scholar
• R. CHAKAROVA, V. PONTIKIS and J. WALLENIUS, “Development of Fe(bcc) Cr Many Body Potential and Cohesion Model”, Delivery report WP6, SPIRE project, EC contract no. FIKW-CT-2000-00058, June 2002 (available at www.neutron.kth.se/publications).
   Google Scholar
• P. OLSSON, L. MALERBA and A. ALMAZOUZI, “A First Step Towards a Multiscale Modelling of Fe-Cr Alloys”, SCK•CEN Report BLG-950, June 2003.
   Google Scholar
• J. WALLENIUS et al., “A First Step Towards a Multiscale Modelling of Fe-Cr Alloys”, Physical Review B, 69, 094103 (2004).
   Google Scholar
• J. WALLENIUS et al., “Development of an EAM Potential for Simulation of Radiation Damage in Fe–Cr Alloys”, Journal of Nuclear Materials, 329-333, Part 2, 1175 (2004).
   Web of Science ®Google Scholar
• L. MALERBA et al., “Molecular Dynamics Simulation of Displacement Cascades in Fe–Cr Alloys” Journal of Nuclear Materials, 329-333, Part 2, 1156 (2004).
   Web of Science ®Google Scholar
• D. TERENTYEV, L. MALERBA, and M. HOU, “In-cascade Interstitial Cluster Formation in Concentrated Ferritic Alloys with Strong Solute-Interstitial Interaction: a Molecular Dynamics Study”, Proceedings of COSIRES 2004, Helsinki, June 2004.
   Google Scholar
• K. ARAKAWA, M. HATANAKA, H. MORI, and K. ONO, “Effects of Chromium on the One-Dimensional Motion of Interstitial-Type Dislocation Loops in Iron”, Journal of Nuclear Materials, 329-333, Part 2, 1194 (2004).
   Web of Science ®Google Scholar
• F.A. GARNER, M.B. TOLOCZKO, and B.H. SENCER, “Comparison of Swelling and Irradiation Creep Behavior of FCC-Austenitic and BCC-Ferritic/Martensitic Alloys at High Neutron Exposure”, Journal of Nuclear Materials, 276, 123 (2000).
   Web of Science ®Google Scholar
• D. TERENTYEV, and L. MALERBA, “Diffusivity of Solute Atoms, Matrix Atoms and Interstitial Atoms in Fe-Cr Alloys: a Molecular Dynamics Study”, Journal of Nuclear Materials, 329-333, Part 2, 1161 (2004).
   Web of Science ®Google Scholar