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R. Klueh, Harries (2001)
Chapter 12—Irradiation Effects on Tensile Behavior
C. Heintze, F. Bergner, M. Hernández-Mayoral (2011)
Ion-irradiation-induced damage in Fe-Cr alloys characterized by nanoindentationJournal of Nuclear Materials, 417
Jinnan Yu, Qunying Huang, F. Wan (2007)
Research and development on the China low activation martensitic steel (CLAM)Journal of Nuclear Materials, 367
G. Was (2007)
Fundamentals of radiation materials science
S. Zinkle, J. Busby (2009)
Structural materials for fission & fusion energyMaterials Today, 12
S. Zinkle, N. Ghoniem (2000)
Operating temperature windows for fusion reactor structural materialsFusion Engineering and Design, 51
J. Salavy, G. Aiello, P. Aubert, L. Boccaccini, M. Daichendt, G. Dinechin, E. Diegele, L. Giancarli, R. Lässer, H. Neuberger, Y. Poitevin, Y. Stephan, G. Rampal, E. Rigal (2009)
Ferritic-martensitic steel test blanket modules: status and future needs for design criteria requirements and fabrication validation.Journal of Nuclear Materials, 386
R. Klueh, D. Harries (2001)
High-Chromium Ferritic and Martensitic Steels for Nuclear Applications
R. Schaeublin, D. Gelles, M. Victoria (2002)
Microstructure of irradiated ferritic/martensitic steels in relation to mechanical propertiesJournal of Nuclear Materials, 307
O. Anderoglu, T. Byun, M. Toloczko, S. Maloy (2012)
Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear ReactorsMetallurgical and Materials Transactions A, 44
A. Kimura, T. Morimura, M. Narui, H. Matsui (1996)
Irradiation hardening of reduced activation martensitic steelsJournal of Nuclear Materials
D. Petti, K. Mccarthy, W. Gulden, S. Piet, Y. Seki, B. Kolbasov (1996)
An overview of safety and environmental considerations in the selection of materials for fusion facilitiesJournal of Nuclear Materials
Siben Jiang, Lei Peng, H. Ge, Qunying Huang, Jingping Xin, Ziqiang Zhao (2014)
He and H irradiation effects on the nanoindentation hardness of CLAM steelJournal of Nuclear Materials, 455
I. Sacksteder, H. Schneider, E. Materna-Morris (2011)
Determining irradiation damage and recovery by instrumented indentation in RAFM steelJournal of Nuclear Materials, 417
G. Was (2007)
Fundamentals of Radiation Materials Science: Metals and Alloys
E. Wakai, M. Ando, T. Sawai, S. Ohnuki (2007)
Effect of Helium and Hydrogen Production on Irradiation Hardening of F82H Steel Irradiated by Ion BeamsMaterials Transactions, 48
(1982)
Effects of Irradiation on Materials
Takuya Yamamoto, G. Odette, H. Kishimoto, J. Rensman, P. Miao (2006)
On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of ∼8Cr tempered martensitic steels : Compilation and analysis of existing dataJournal of Nuclear Materials, 356
E. Little, L. Stoter (1982)
Microstructural Stability of Fast Reactor Irradiated 10–12%Cr Ferritic-Martensitic Stainless SteelsASTM special technical publications, 782
H. Ge, Lei Peng, Yong Dai, Qunying Huang, M. Ye (2016)
Tensile properties of CLAM steel irradiated up to 20.1 dpa in STIP-VJournal of Nuclear Materials, 468
E. Materna-Morris, A. Möslang, H. Schneider (2013)
Tensile and low cycle fatigue properties of EUROFER97-steel after 16.3 dpa neutron irradiation at 523, 623 and 723 KJournal of Nuclear Materials, 442
(2017)
SRIM-2008 program
T. Shen, Z. Wang, C. Yao, Jianrong Sun, Y. Li, K. Wei, Yabin Zhu, L. Pang, M. Cui, J. Wang, Huiping Zhu (2013)
The sink effect of the second-phase particle on the cavity swelling in RAFM steel under Ar-ion irradiation at 773 KNuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms, 307
A. Álamo, M. Horsten, X. Averty, E. Materna-Morris, M. Rieth, J. Brachet (2000)
Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250–450°CJournal of Nuclear Materials, 283
A. Tavassoli (1998)
Materials design data for fusion reactorsJournal of Nuclear Materials, 258263
M. Roldán, P. Fernández, Joaquin Rams, D. Jiménez-Rey, C. Ortiz, R. Vila (2014)
Effect of helium implantation on mechanical properties of EUROFER97 evaluated by nanoindentationJournal of Nuclear Materials, 448
T. Muroga, M. Gasparotto, S. Zinkle (2002)
Overview of materials research for fusion reactorsFusion Engineering and Design, 61
Qunying Huang, Jian-gang Li, Yixue Chen (2004)
Study of irradiation effects in China low activation martensitic steel CLAMJournal of Nuclear Materials, 329
T. Hirose, N. Okubo, H. Tanigawa, M. Ando, M. Sokolov, R. Stoller, G. Odette (2011)
Irradiation hardening in F82H irradiated at 573 K in the HFIRJournal of Nuclear Materials, 417
Chunjing Li, Qunying Huang, P. Zhang (2007)
Preliminary experimental study on Hot Isostatic Pressing diffusion bonding for CLAM/CLAM, 82
M. Ando, H. Tanigawa, S. Jitsukawa, T. Sawai, Y. Katoh, A. Kohyama, K. Nakamura, H. Takeuchi (2002)
Evaluation of hardening behaviour of ion irradiated reduced activation ferritic/martensitic steels by an ultra-micro-indentation techniqueJournal of Nuclear Materials, 307
A. Tavassoli (2002)
Present limits and improvements of structural materials for fusion reactors – a reviewJournal of Nuclear Materials, 302
H. Ogiwara, A. Kohyama, H. Tanigawa, H. Sakasegawa (2006)
Irradiation-induced hardening mechanism of ion irradiated JLF-1 to high fluencesFusion Engineering and Design, 81
M. Roldán, P. Fernández, J. Rams, D. Jiménez-Rey, E. Materna-Morris, M. Klimenkov (2015)
Comparative study of helium effects on EU-ODS EUROFER and EUROFER97 by nanoindentation and TEMJournal of Nuclear Materials, 460
(2007)
Was, Fundamentals of Radiation Materials Science, p
Abstract The irradiation-induced hardening and softening of CLAM steel irradiated with 3.5 MeV Fe13+ ions at temperatures of 300 °C and 550 °C were investigated by nanoindentation tests in combination with microstructures. Irradiation- induced hardening occurred in the steel irradiated at 300 °C to doses of 0.46 dpa, 0.94 dpa, and 2.79 dpa. The hardening occurred at 300 °C is mainly attributed to the formation of irradiation-produced dislocation loops and a network of tangled dislocations in the irradiated steel samples. Significant hardening was found in the steel irradiated at 550 °C to 0.38 dpa. On the contrary, irradiation-induced softening occurred in the steel irradiated at 550 °C to both 0.76 dpa and 2.75 dpa. Irradiation-produced dislocation loops are not dominant effect on the irradiation hardening of the steel samples irradiated at 550 °C. The hardening and softening of the irradiated steel were explained in terms of the irradiation-produced defects and recovery process occurred during the irradiation.
"Metals and Materials International" – Springer Journals
Published: Nov 1, 2017
Keywords: Metallic Materials; Manufacturing, Machines, Tools, Processes; Magnetism, Magnetic Materials; Engineering Thermodynamics, Heat and Mass Transfer; Characterization and Evaluation of Materials; Solid Mechanics
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