Ferritic/martensitic(F/M) steels have been recommended as one of the candidate materials for supercritical water cooled reactor(SCWR) in-core components use for its high thermal conductivity,low thermal expansion coefficient and inherently good dimensional stability under irradiation condition in comparison to austenitic steel.CNS-Ⅱ F/M steel which has good mechanical properties was one of the 9-12Cr F/M steels designed for SCWR in the previous work.In this study a modified CNS-Ⅱ F/M steel was used and it's ultimate tensile strength was 925 MPa at room temperature and 483 MPa at 600 ℃ after optimizing heat treatment parameter.The ductile to brittle transition temperature of modified CNS-Ⅱ F/M steel is-55 ℃.Those are at the same level or even higher than that of CNS-Ⅱ and some commercial F/M steels nominated for SCWR in-core component use.The transmission electron microscope(TEM) results showed that the mechanical properties of the tempered martensite was closely related to the decomposition stage of the martensite.
参考文献
[1] | Abram T;Ion S .Generation-IV Nuclear Power:A Review of the State of the Science[J].Energy Policy,2008,36(12):4323. |
[2] | Murty, KL;Charit, I .Structural materials for Gen-IV nuclear reactors: Challenges and opportunities[J].Journal of Nuclear Materials,2008(1/2):189-195. |
[3] | Yvon, P.;Carre, F. .Structural materials challenges for advanced reactor systems[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2009(2):217-222. |
[4] | Klueh RL .Reduced-activation steels: Future development for improved creep strength[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2008(2):159-166. |
[5] | Static recovery of tempered lath martensite microstructures during long-term aging in 9-12% Cr heat resistant steels[J].Materials Letters,2009(28):2423. |
[6] | Schneider A;Inden G .Simulation of the kinetics of precipitation reactions in ferritic steels[J].Acta materialia,2005(2):519-531. |
[7] | Lindau R;Moslang A;Sehirra M .Thermal and Mechanical Behavior of the Redueed-Activation-Ferritic-Martensitie Steel EUROFER[J].Fusion Engineering and Design,2002,61-62(12):659. |
[8] | Tong, Z;Dai, Y .The microstructure and tensile properties of ferritic/martensitic steels T91, Eurofer-97 and F82H irradiated up to 20 dpa in STIP-III[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2010(1/3):43-48. |
[9] | Maloy Stuart A;Romero T;James M R et al.Tensile Testing of EP-823 and HT-9 After Irradiation in STIP Ⅱ[J].Journal of Nuclear Materials,2006,356(1/2/3):56. |
[10] | Klueh RL;Shiba K;Sokolov MA .Embrittlement of irradiated ferritic/martensitic steels in the absence of irradiation hardening[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2008(3):427-437. |
[11] | Rieth M;Dafferner B;Rohrig H-D .Embrittlement Behavior of Different International Low Activation Alloys After Neutron Irradiation[J].Journal of Nuclear Materials,1998,258- 263:1147. |
[12] | Klueh RL;Sokolov MA;Hashimoto N .Mechanical properties of unirradiated and irradiated reduced-activation martensitic steels with and without nickel compared to properties of commercial steels[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2008(1/2):220-228. |
[13] | Dai Y;Marmy P .Charpy impact tests on martensitic/ferritic steels after irradiation in SINQ Target-3[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2005(1/3):247-252. |
[14] | J. Pesicka;R. Kuzel;A. Dronhofer;G. Eggeler .The evolution of dislocation density during heat treatment and creep of tempered martensite ferritic steels[J].Acta materialia,2003(16):4847-4862. |
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