Ferritic-martensitic steels for fission and fusion applications
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Céline Cabet | Hiroyasu Tanigawa | Ermile Gaganidze | J. Henry | E. Gaganidze | J. Henry | H. Tanigawa | C. Cabet | F. Dalle | F. Dalle
[1] R. Klueh,et al. Embrittlement of irradiated ferritic/martensitic steels in the absence of irradiation hardening , 2008 .
[2] S. Rogozhkin,et al. Atom probe study of radiation induced precipitates in Eurofer97 Ferritic-Martensitic steel irradiated in BOR-60 reactor , 2013, Inorganic Materials: Applied Research.
[3] M. Rieth,et al. The effect of tantalum on the mechanical properties of a 9Cr 2W 0.25V 0.07Ta 0.1C steel , 1999 .
[4] N. Baluc,et al. The mechanical properties and microstructure of the OPTIMAX series of low activation ferritic–martensitic steels , 2000 .
[5] Kenneth William Burn,et al. Status and trend of core design activities for heavy metal cooled accelerator driven system , 2006 .
[6] Mike Garrett,et al. TERRAPOWER, LLC TRAVELING WAVE REACTOR DEVELOPMENT PROGRAM OVERVIEW , 2013 .
[7] Gaurav Gupta,et al. Corrosion and stress corrosion cracking in supercritical water , 2007 .
[8] A. Kohyama,et al. Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773 K up to 5 dpa , 2007 .
[9] F. Balbaud-Célérier,et al. Effect of oxygen on liquid sodium embrittlement of T91 martensitic steel , 2013 .
[10] J. Aktaa,et al. Investigation of microstructure defects in EUROFER97 under He⁺/Fe³⁺ dual ion beam irradiation , 2018 .
[11] B. Raj,et al. Measurement of transformation temperatures and specific heat capacity of tungsten added reduced activation ferritic–martensitic steel , 2009 .
[12] J. Aktaa,et al. Review and critical assessment of dislocation loop analyses on EUROFER 97 , 2018 .
[13] Céline Cabet,et al. Corrosion of high temperature metallic materials in VHTR , 2009 .
[14] Steven J. Zinkle,et al. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules , 2008 .
[15] K. Suzuki,et al. Effect of tempering temperature on Z-phase formation and creep strength in 9Cr–1Mo–V–Nb–N steel , 2008 .
[16] M. Tamura,et al. Mechanical properties of welded joints of the reduced-activation ferritic steel: 8% Cr-2% W-0.2% V-0.04% Ta-Fe , 1991 .
[17] Ronald L. Klueh,et al. Microstructural analysis of neutron-irradiated martensitic steels☆ , 1996 .
[18] G. Was,et al. The mechanism of radiation-induced segregation in ferritic–martensitic alloys , 2014 .
[19] John C. Lippold,et al. Transformation and tempering behavior of 12Cr-1Mo-0.3V martensitic stainless steel weldments , 1981 .
[20] Y. Yano,et al. Tensile and transient burst properties of advanced ferritic/martensitic steel claddings after neutron irradiation , 2007 .
[21] R. Chaouadi,et al. Effect of irradiation-induced plastic flow localization on ductile crack resistance behavior of a 9%Cr tempered martensitic steel , 2008 .
[22] E. Diegele,et al. Current status and recent research achievements in ferritic/martensitic steels , 2014 .
[23] M. Abe,et al. Evaluation of magnetic fields due to the ferromagnetic vacuum vessel and their influence on plasma discharge in tokamak devices , 1999 .
[24] Ivan Tournié,et al. Macroscopic results of long-term creep on a modified 9Cr–1Mo steel (T91) , 2009 .
[25] Takanori Hirose,et al. Radiological assessment of the limits and potential of reduced activation ferritic/martensitic steels , 2014 .
[26] A. Almazouzi,et al. Assessment of the lifetime of the beam window of MEGAPIE target liquid metal container , 2006 .
[27] F. Mann,et al. Reduced activation calculations for the STARFIRE first wall , 1984 .
[28] T. Kondo,et al. Accumulation of engineering data for practical use of reduced activation ferritic steel: 8%Cr2%W0.2%V0.04%TaFe , 1992 .
[29] B. A. Vasiliev,et al. Structural materials for fusion power reactors—the RF R&D activities , 2007 .
[30] H.-C. Schneider,et al. Tensile behavior of RAFM alloys after neutron irradiation of up to 16.3 dpa between 250 and 450 °C , 2014 .
[31] Y. Carlan,et al. Effect of thermal aging on the microstructure and mechanical properties of 7–11 CrW steels , 2000 .
[32] Akira Kohyama,et al. Dependence of impact properties on irradiation temperature in reduced-activation martensitic steels , 1998 .
[33] Ronald L. Klueh,et al. Embrittlement of CrMo steels after low fluence irradiation in HFIR , 1995 .
[34] M. Rieth,et al. Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250–450°C , 2000 .
[35] Jarir Aktaa,et al. Study of helium embrittlement in boron doped EUROFER97 steels , 2009 .
[36] A. Möslang,et al. Characterization of radiation induced defects in EUROFER 97 after neutron irradiation , 2011 .
[37] N. Baluc,et al. Investigation of liquid LBE embrittlement effects on irradiated ferritic/martensitic steels by slow-strain-rate tensile tests , 2012 .
[38] G. Odette,et al. Development of mechanical property correlation methodology for fusion environments , 1979 .
[39] J. Weertman,et al. Investigation of microstructural changes in a ferritic steel caused by high temperature fatigue , 1988 .
[40] Jarir Aktaa,et al. Assessment of neutron irradiation effects on RAFM steels , 2013 .
[41] H. Liao,et al. Investigation on microstructure and properties of narrow-gap laser welding on reduced activation ferritic/martensitic steel CLF-1 with a thickness of 35 mm , 2018 .
[42] Alessandro Alemberti,et al. Overview of lead-cooled fast reactor activities , 2014 .
[43] K. Shiba,et al. Effect of helium production on swelling of F82H irradiated in HFIR , 2000 .
[44] K. Wolski,et al. Influence of CO2 purity on the oxidation of a 12Cr ferritic – martensitic steel at 550°C and importance of the initial stage , 2012 .
[45] K. Sun,et al. Emulation of reactor irradiation damage using ion beams , 2014 .
[46] Meimei Li,et al. Microstructural evolution of neutron-irradiated T91 and NF616 to ∼4.3 dpa at 469 °C ☆ , 2017 .
[47] Jean-Charles Jaboulay,et al. Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO , 2017 .
[48] J. Aktaa,et al. Mechanical properties and TEM examination of RAFM steels irradiated up to 70 dpa in BOR-60 , 2011 .
[49] A. Weisenburger,et al. T91 cladding tubes with and without modified FeCrAlY coatings exposed in LBE at different flow, stress and temperature conditions , 2008 .
[50] Alfons Weisenburger,et al. Corrosion, Al containing corrosion barriers and mechanical properties of steels foreseen as structural materials in liquid lead alloy cooled nuclear systems , 2011 .
[51] Tetsuji Noda,et al. Development of low activation Ferritic steels , 1986 .
[52] Heishichiro Takahashi,et al. Effects of Fast Reactor Irradiation Conditions on Tensile and Transient Burst Properties of Ferritic/Martensitic Steel Claddings , 2007 .
[53] C. Petersen,et al. Post irradiation examination of RAF/M steels after fast reactor irradiation up to 33 dpa and < 340⁰C (ARBOR 1) , 2010 .
[54] M. V. Leont’eva-Smirnova,et al. Advances in Structural Materials for Fast-Reactor Cores , 2016 .
[55] A. Kohyama,et al. Microstructural developments in Fe-Cr-W low activation ferritic steels under dual beam charged particle irradiation , 1991 .
[56] Michael L Santella,et al. Issues in replacing Cr-Mo steels and stainless steels with 9Cr-1Mo-V steel , 2004 .
[57] I. Wright,et al. A review of the oxidation behaviour of structural alloys in steam , 2010 .
[58] D. Stow,et al. Void-swelling in irons and ferritic steels: II. An experimental survey of materials irradiated in a fast reactor , 1979 .
[59] R. Klueh,et al. Charpy Impact Properties of Reduced-Activation Ferritic/Martensitic Steels Irradiated in HFIR up to 20 dpa , 2003 .
[60] Wei Qu,et al. Progress in corrosion resistant materials for supercritical water reactors , 2009 .
[61] C. Petersen,et al. Tensile and low cycle fatigue properties of different ferritic/martensitic steels after the fast reactor irradiation ‘ARBOR 1’ , 2009 .
[62] S. Zinkle,et al. Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications , 2017 .
[63] Isabelle Monnet,et al. Cyclically induced softening due to low-angle boundary annihilation in a martensitic steel , 2005 .
[64] V. Chernov,et al. Investigation of heat treatment conditions on the structure of 12% chromium reduced activation steels , 2002 .
[65] D. Gelles. Swelling in several commercial alloys irradiated to very high neutron fluence , 1984 .
[66] L. Giancarli,et al. Some radiological limitations on the compositions of low-activation materials for power reactors , 1988 .
[67] H. Böhm,et al. Einfluss einer phasenumwandlung auf das auftreten der hochtemperaturversprödung nach neutronenbestrahlung , 1967 .
[68] Yong Dai,et al. Materials researches at the Paul Scherrer Institute for developing high power spallation targets , 2009 .
[69] T. Byun,et al. Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors , 2012, Metallurgical and Materials Transactions A.
[70] A. Pineau,et al. High-temperature mechanical properties improvement on modified 9Cr―1Mo martensitic steel through thermomechanical treatments , 2010 .
[71] J. Bourgon,et al. Wetting by liquid sodium and fracture path analysis of sodium induced embrittlement of 304L stainless steel , 2018 .
[72] Sanghoon Noh,et al. Effects of alloying elements and heat treatments on mechanical properties of Korean reduced-activation ferritic–martensitic steel , 2014 .
[73] F. Garner,et al. Irradiation creep and void swelling of two LMR heats of HT9 at ∼ 400°C and 165 dpa , 1996 .
[74] A. Kohyama,et al. Irradiation response of a reduced activation Fe-8Cr-2W martensitic steel (F82H) after FFTF irradiation , 1992 .
[75] Y. Yano,et al. Effect of high dose/high temperature irradiation on the microstructure of heat resistant 11Cr ferritic/martensitic steels , 2009 .
[76] A. Möslang,et al. Fatigue tests on a ferritic-martensitic steel at 420°C: Comparison between in-situ and postirradiation properties , 1994 .
[77] J. Aktaa,et al. TEM study and modeling of bubble formation in dual-beam He+/Fe3+ ion irradiated EUROFER97 , 2017 .
[78] A. Hishinuma,et al. Swelling of F82H irradiated at 673 K up to 51 dpa in HFIR , 2000 .
[79] C. McHargue,et al. Materials requirements for fusion reactors , 1978 .
[80] M. Tabarant,et al. Single Crystal and Sintered Alumina Corrosion in Liquid Sodium , 2017, Oxidation of Metals.
[81] E. Lucon,et al. Overview of the tensile properties of EUROFER in the unirradiated and irradiated conditions , 2009 .
[82] Anton Möslang,et al. Influence of helium on impact properties of reduced-activation ferritic/martensitic Cr-steels , 1999 .
[83] Y. Dai,et al. Neutron/proton irradiation and He effects on the microstructure and mechanical properties of ferritic/martensitic steels T91 and EM10 , 2011 .
[84] S. Dudarev,et al. Materials engineering and design for fusion—Towards DEMO design criteria , 2018, Fusion Engineering and Design.
[85] Fujio Abe,et al. Precipitate design for creep strengthening of 9% Cr tempered martensitic steel for ultra-supercritical power plants , 2008, Science and technology of advanced materials.
[86] W. Blum,et al. Effects of cyclic deformation on subgrain evolution and creep in 9–12% Cr-steels , 2005 .
[87] J. Aktaa,et al. Microstructural characterization of Eurofer-97 and Eurofer-ODS steels before and after multi-beam ion irradiations at JANNUS Saclay facility , 2015 .
[88] M. Narui,et al. Irradiation embrittlement of neutron-irradiated low activation ferritic steels , 1988 .
[89] Qunying Huang,et al. Recent progress of R&D activities on reduced activation ferritic/martensitic steels , 2013 .
[90] T. Lechtenberg. Irradiation effects in ferritic steels , 1985 .
[91] Mikhail A. Sokolov,et al. Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications , 2009 .
[92] H. Schroeder,et al. The influence of helium on the high temperature mechanical properties of DIN 1.4914 martensitic steel , 1988 .
[93] A. Möslang,et al. Micro-structural effects of irradiation temperature and helium content in neutron irradiated B-alloyed Eurofer97-1 steel , 2018, Nuclear Materials and Energy.
[94] Y. Katoh,et al. Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors , 2016 .
[95] G. Benamati,et al. Influence of temperature on the interaction mode of T91 and AISI 316L steels with Pb–Bi melt saturated by oxygen , 2008 .
[96] A. Kohyama,et al. Void swelling in reduced activation ferritic/martensitic steels under ion-beam irradiation to high fluences , 2002 .
[97] Ronald L. Klueh,et al. Ferritic/martensitic steels for next-generation reactors , 2007 .
[98] M. Rieth,et al. Improvement of reduced activation 9%Cr steels by ausforming , 2016 .
[99] H. Matsui,et al. Designation of alloy composition of reduced-activation martensitic steel , 1994 .
[100] P. Skeldon,et al. The liquid metal embrittlement of iron and ferritic steels in sodium , 1995 .
[101] K. Shiba,et al. Embrittlement of reduced-activation ferritic/martensitic steels irradiated in HFIR at 300°C and 400°C , 2000 .
[102] Rafael Fernandez,et al. MYRRHA – A multi-purpose fast spectrum research reactor , 2012 .
[103] Knud Thomsen,et al. MEGAPIE at SINQ – The first liquid metal target driven by a megawatt class proton beam , 2008 .
[104] Y. Katoh,et al. Development of castable nanostructured alloys as a new generation RAFM steels , 2018, Journal of Nuclear Materials.
[105] W. Chen,et al. The application of martensitic stainless steels in long lifetime fusion first wall/blankets☆ , 1979 .
[106] Steven J. Zinkle,et al. Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications , 2017 .
[107] R. Montanari,et al. Structural and mechanical properties of welded joints of reduced activation martensitic steels , 2002 .
[108] Mychailo B. Toloczko,et al. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure , 2000 .
[109] S. Ohtsuka,et al. Tensile properties and hardness of two types of 11Cr-ferritic/martensitic steel after aging up to 45,000 h , 2016 .
[110] A. M. Lancha,et al. Grain boundary microchemistry and metallurgical characterization of Eurofer'97 after simulated service conditions , 2004 .
[111] H. Matsui,et al. Void swelling of Japanese candidate martensitic steels under FFTF/MOTA irradiation , 1996 .
[112] R. Klueh,et al. Impact behavior of reduced-activation steels irradiated to 24 dpa , 1996 .
[113] S. Ukai,et al. Irradiation creep of 11Cr-0.5Mo-2W,V,Nb ferritic-martensitic, modified 316, and 15Cr-20Ni austenitic S.S. irradiated in FFTF to 103-206 dpa , 2000 .
[114] J. Vogt,et al. Heat treatment effect of T91 martensitic steel on liquid metal embrittlement , 2008 .
[115] M. Lambrecht,et al. Comparison of the mechanical properties of T91 steel from the MEGAPIE, and TWIN-ASTIR irradiation programs , 2016 .
[116] H. Böhm,et al. Investigation of radiation induced high-temperature embrittlement of ferritic steels in the temperature range of the α-γ-transformation , 1969 .
[117] C. Parish,et al. Microstructure and property tailoring of castable nanostructured alloys through thermomechanical treatments , 2018, Journal of Nuclear Materials.
[118] S. Dudarev,et al. An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation , 2012 .
[119] Y. Sasaki,et al. Effect of thermo-mechanical treatment on toughness of 9Cr-W ferritic-martensitic steels during aging , 1991 .
[120] F. Garner,et al. Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors , 2004 .
[121] M. Tabarant,et al. Comparative oxidation behaviour of Fe-9Cr steel in CO2 and H2O at 550 °C: Detailed analysis of the inner oxide layer , 2015 .
[122] Yves Poitevin,et al. The European ITER Test Blanket Modules: EUROFER97 material and TBM’s fabrication technologies development and qualification , 2017 .
[123] E. J. Fulton,et al. Voids in Irradiated Stainless Steel , 1967, Nature.
[124] G. R. Odette,et al. Helium effects on microstructural evolution in tempered martensitic steels: In situ helium implanter studies in HFIR , 2009 .
[125] Baldev Raj,et al. Current Status of Fast Reactors and Future Plans in India , 2011 .
[126] X. Jia,et al. The impact of irradiation temperature on the microstructure of F82H martensitic/ferritic steel irradiated in a proton and neutron mixed spectrum , 2002 .
[127] S. Jitsukawa,et al. Ferritic/martensitic steels – overview of recent results , 2002 .
[128] M. Rieth,et al. TEM characterization on new 9% Cr advanced steels thermomechanical treated after tempering , 2018 .
[129] C. Petersen,et al. Impact property degradation of ferritic/martensitic steels after the fast reactor irradiation ‘ARBOR 1’ , 2007 .
[130] R. L. Klueh,et al. The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications ☆ , 1985 .
[131] J. Aktaa,et al. Microstructural defects in EUROFER 97 after different neutron irradiation conditions , 2016 .
[132] S. Ohtsuka,et al. Weldability of dissimilar joint between PNC-FMS and Type 316 steel under electron beam welding , 2014 .
[133] R. Klueh. Analysis of swelling behaviour of ferritic/martensitic steels , 2018, Philosophical Magazine.
[134] L. W. Graham. Corrosion of metallic materials in HTR-helium environments , 1990 .
[135] J. Aktaa,et al. The effects of helium on the embrittlement and hardening of boron doped EUROFER97 steels , 2008 .
[136] A. Alamo,et al. Mechanical properties of 9Cr martensitic steels and ODS-FeCr alloys after neutron irradiation at 325 °C up to 42 dpa , 2007 .
[137] F. Garner,et al. Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 °C , 2009 .
[138] J. Aktaa,et al. Quantitative TEM analysis of precipitation and grain boundary segregation in neutron irradiated EUROFER 97 , 2014 .
[139] T. Nozawa,et al. Effect of Helium on Irradiation Creep Behavior of B-Doped F82H Irradiated in HFIR , 2015 .
[140] Jose Galabert,et al. The European ITER Test Blanket Modules: Current status of fabrication technologies development and a way forward , 2015 .
[141] Takanori Hirose,et al. Long-term properties of reduced activation ferritic/martensitic steels for fusion reactor blanket system , 2011 .
[142] A. Pineau,et al. Lifetime prediction of 9–12%Cr martensitic steels subjected to creep–fatigue at high temperature , 2010 .
[143] Ronald L. Klueh,et al. Development of ferritic steels for reduced activation: The US program , 1986 .
[144] A. Möslang,et al. Effect of 16.3 dpa neutron irradiation on fatigue lifetime of the RAFM steel EUROFER97 , 2011 .
[145] F. Balbaud-Célérier,et al. High temperature oxidation of Fe-9Cr-1Mo steel in stagnant liquid lead-bismuth at several temperatures and for different lead contents in the liquid alloy , 2008 .
[146] E. Wakai,et al. Reduction method of DBTT shift due to irradiation for reduced-activation ferritic/martensitic steels , 2010 .
[147] E. Diegele,et al. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts , 2005 .
[148] H.-C. Schneider,et al. Tensile and low cycle fatigue properties of EUROFER97-steel after 16.3 dpa neutron irradiation at 523, 623 and 723 K , 2013 .
[149] L. Schäfer,et al. The development of ferritic-martensitic steels with reduced long-term activation , 1994 .
[150] K. Sridharan,et al. Role of grain boundary engineering in the SCC behavior of ferritic–martensitic alloy HT-9 , 2007 .
[151] A. Pineau,et al. Characterization of a boron alloyed 9Cr3W3CoVNbBN steel and further improvement of its high-temperature mechanical properties by thermomechanical treatments , 2013 .
[152] Ronald L. Klueh,et al. Microstructure-mechanical properties correlation of irradiated conventional and reduced-activation martensitic steels , 1995 .
[153] F. Balbaud-Célérier,et al. Modelling of the oxide scale formation on Fe‐Cr steel during exposure in liquid lead‐bismuth eutectic in the 450–600 °C temperature range , 2011 .
[154] M. Tabarant,et al. Oxidation of 316L(N) stainless steel in liquid sodium at 650 °C , 2014 .
[155] Yican Wu,et al. Status of R&D activities on materials for fusion power reactors , 2007 .
[156] C. R. Eiholzer,et al. Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ~ 400°C☆ , 1994 .
[157] L. Shao,et al. Radiation response of alloy T91 at damage levels up to 1000 peak dpa , 2016 .
[158] J. W. Bennett,et al. Materials requirements for liquid metal fast breeder reactors , 1978 .
[159] R. Rolli,et al. Effect of helium on tensile properties and microstructure in 9%Cr–WVTa–steel after neutron irradiation up to 15 dpa between 250 and 450 °C , 2009 .
[160] R. Schäublin,et al. Helium and point defect accumulation: (i) microstructure and mechanical behaviour , 2008 .
[161] S. David,et al. Welding and weldability of candidate ferritic alloys for future advanced ultrasupercritical fossil power plants , 2013 .
[162] D. Gelles. Microstructural examination of several commercial alloys neutron irradiated to 100 dpa , 1987 .
[163] J. V. D. Bosch,et al. SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184 dpa at 413 °C , 2013 .
[164] H.-C. Schneider,et al. High-dose neutron irradiation embrittlement of RAFM steels , 2006 .
[165] G. J. Butterworth,et al. Development of low-activation martensitic stainless steels , 1986 .
[166] J. Aktaa,et al. Embrittlement behaviour of low-activation alloys with reduced boron content after neutron irradiation , 2003 .
[167] A. Armas,et al. Cyclic instability of martensite laths in reduced activation ferritic/martensitic steels , 2004 .
[168] M. Aoki,et al. Evaluation of Carburization and Decarburization Behavior of Fe-9Cr-Mo Ferritic Steels in Sodium Environment , 1992 .
[169] S. Jitsukawa,et al. Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures , 1998 .
[170] T. Mizuno,et al. Tensile Properties of llCr-0.5Mo-2W, V, Nb Stainless Steel in LMFBR Environment , 2000 .
[171] G. Gupta,et al. Tensile and stress corrosion cracking behavior of ferritic–martensitic steels in supercritical water , 2009 .
[172] K. Sridharan,et al. Oxidation of 9Cr oxide dispersion strengthened steel exposed in supercritical water , 2007 .
[173] A. Hishinuma,et al. Microstructure of welded and thermal-aged low activation steel F82H IEA heat , 2000 .
[174] T. Kruml,et al. Low cycle fatigue of Eurofer 97 , 2008 .
[175] Manabu Tamura,et al. Development of potential low activation ferritic and austenitic steels , 1986 .
[176] Y. Lejeail,et al. Creep behaviour and failure modelling of modified 9Cr1Mo steel , 2012 .
[177] R. Klueh,et al. Impact behavior of 9-Cr and 12-Cr ferritic steels after low-temperature irradiation , 1988 .
[178] R. Klueh,et al. Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR☆ , 1984 .
[179] P. Dubuisson,et al. Pre- and post-irradiation mechanical properties of ferritic-martensitic steels for fusion applications: EM10 base metal and EM10/EM10 welds , 1994 .
[180] F. Garner,et al. Influence of radiation on material properties: ASTM 13th international symposium (Part II) , 1987 .
[181] G. Was,et al. The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels , 2017 .
[182] Y. Carlan,et al. A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels , 2003 .
[183] E. E. Bloom. Mechanical properties of materials in fusion reactor first-wall and blanket systems , 1979 .
[184] E. Materna-Morris,et al. Determining irradiation damage and recovery by instrumented indentation in RAFM steel , 2011 .
[185] R. W. Conn,et al. Low activation materials for fusion applications , 1984 .
[186] David S. Gelles,et al. Progress and critical issues of reduced activation ferritic/martensitic steel development , 2000 .
[187] J. Aktaa,et al. Quantitative characterization of microstructural defects in up to 32 dpa neutron irradiated EUROFER97 , 2012 .
[188] K. Anderko. Zur eignung warmfester vergütungsstähle mit 9 bis 12% chrom für komponenten im kern schneller reaktoren — ein überblick , 1980 .
[189] M. Williams,et al. The Calculated Performance of Various Structural Materials in Fusion-Reactor Blankets , 1976 .
[190] E. Diegele,et al. Development of EUROFER97 database and material property handbook , 2018, Fusion Engineering and Design.
[191] P. Marmy,et al. The effect of low dose irradiation on the impact fracture energy and tensile properties of pure iron and two ferritic martensitic steels , 1998 .
[192] D. S. Gelles,et al. Comments on "Embrittlement of CrMo steels after low fluence irradiation in high flux isotope reactor" , 1996 .
[193] P. Bocquet,et al. Properties of heavy components of steel grade 91 and their welds , 1993 .
[194] D. Struwe,et al. European lead fast reactor—ELSY , 2011 .
[195] M. L. Hamilton,et al. Mechanical property changes of low activation ferritic/martensitic steels after neutron irradiation , 1999 .
[196] E. Wakai,et al. Effect of gas atoms and displacement damage on mechanical properties and microstructures of F82H , 2006 .
[197] Toshiyuki Takagi,et al. Progress of electromagnetic analysis for fusion reactors , 1998 .
[198] Q. Yan,et al. Void swelling in ferritic-martensitic steels under high dose ion irradiation: Exploring possible contributions to swelling resistance , 2016 .
[199] Mikhail A. Sokolov,et al. Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket , 2011 .
[200] C. Petersen,et al. The ARBOR irradiation project , 2002 .
[201] A. V. Kozlov,et al. Development of structural steel for fuel elements and fuel assemblies of sodium-cooled fast reactors , 2010 .
[202] D. R. Harries,et al. Materials research and development for NET , 1985 .
[203] Michael Rieth,et al. Embrittlement behaviour of different international low activation alloys after neutron irradiation , 1998 .
[204] Pascal Yvon,et al. Update of the French R&D strategy on gas-cooled reactors , 2010 .
[205] F. Rouillard,et al. Corrosion of 9-12Cr ferritic–martensitic steels in high-temperature CO2 , 2016 .
[206] Kazuhiro Kimura,et al. Inherent creep strength and long term creep strength properties of ferritic steels , 1997 .
[207] Ying Yang,et al. Effects of Alloying Elements and Thermomechanical Treatment on 9Cr Reduced Activation Ferritic-Martensitic (RAFM) Steels , 2013 .
[208] R. Klueh,et al. Impact behavior of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated in HFIR☆ , 1991 .
[209] Enrico Lucon,et al. Irradiation resistance of Eurofer97 at 300 °C up to 10 dpa , 2004 .
[210] R. Klueh. Reduced-activation steels: Future development for improved creep strength , 2008 .
[211] Shoji Kotake,et al. Evaluation of JSFR Key Technologies , 2012 .
[212] Shoji Kotake,et al. Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor , 2011 .
[213] D. Dulieu,et al. The development of low-activation martensitic 9 and 11%Cr,W,V stainless steels for fusion reactor applications , 1988 .
[214] G. Srinivasan,et al. Development of filler wires for welding of reduced activation ferritic martenstic steel for India's test blanket module of ITER , 2011 .
[215] R. Klueh,et al. Heat treatment effects on impact toughness of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated to 100 dpa , 1998 .
[216] D. Gilbon,et al. Behaviour of different ferritic steels under ion, electron and fast neutron irradiation☆ , 1988 .
[217] A. Alamo,et al. Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325 °C up to 78 dpa , 2011 .
[218] R. Klueh,et al. Hardening mechanisms of reduced activation ferritic/martensitic steels irradiated at 300 °C , 2009 .
[219] B. Fournier,et al. Comparison of various 9–12%Cr steels under fatigue and creep-fatigue loadings at high temperature , 2011 .
[220] Baldev Raj,et al. Progress in the development of reduced activation ferritic-martensitic steels and fabrication technologies in India , 2010 .
[221] A. Möslang,et al. Helium influence on the microstructure and swelling of 9%Cr ferritic steel after neutron irradiation to 16.3 dpa , 2014 .
[222] R. Sorci,et al. Development of innovative steels and thermo-mechanical treatments for DEMO high operating temperature blanket options , 2018, Nuclear Materials and Energy.
[223] P. Dubuisson,et al. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix , 1993 .