메뉴 건너뛰기




Volumn 44, Issue 12, 2007, Pages 1535-1542

Effects of fast reactor irradiation conditions on tensile and transient burst properties of ferritic/martensitic steel claddings

Author keywords

Ferritic martensitic steel; Fuel test subassembly; Tensile property; Transient burst property

Indexed keywords

CLADDING (COATING); FAST REACTORS; IRRADIATION; MARTENSITE; TENSILE PROPERTIES;

EID: 38349188701     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.3327/jnst.44.1535     Document Type: Article
Times cited : (13)

References (25)
  • 1
    • 38349100659 scopus 로고    scopus 로고
    • ORNL/TM-2003/244/R2
    • Dec. 31
    • W. R. Corwin, T. D. Burchell, W. G. Halsey et al., "Updated Generation IV Reactors Integrated Materials Technology Program Plan Revision 2," ORNL/TM-2003/244/R2, Dec. 31 (2005).
    • (2005)
    • Corwin, W.R.1    Burchell, T.D.2    Halsey, W.G.3
  • 2
    • 0027878549 scopus 로고
    • Tube manufacturing and mechanical properties of oxide dispersion strengthened ferritic steel
    • S. Ukai, M. Harada, H. Okada et al., "Tube manufacturing and mechanical properties of oxide dispersion strengthened ferritic steel," J. Nucl. Mater., 204, 74-80 (1993).
    • (1993) J. Nucl. Mater , vol.204 , pp. 74-80
    • Ukai, S.1    Harada, M.2    Okada, H.3
  • 3
    • 38349122690 scopus 로고    scopus 로고
    • Japan Atomic Energy Agency and The Japan Atomic Power Company, Feasibility Study on Commercialized Fast Reactor Cycle Systems-Phase II Final Report-, Japan Atomic Energy Agency Report, JAEA-Evaluation 2006-02 [in Japanese].
    • Japan Atomic Energy Agency and The Japan Atomic Power Company, Feasibility Study on Commercialized Fast Reactor Cycle Systems-Phase II Final Report-, Japan Atomic Energy Agency Report, JAEA-Evaluation 2006-02 [in Japanese].
  • 4
    • 0034546465 scopus 로고    scopus 로고
    • Irradiation creep of 11Cr-0.5Mo-2W, V, Nb ferritic-martensitic, modified 316, and 15Cr-20Ni austenitic S.S. irradiated in FFTF to 103206 dpa
    • A. Uehira, S. Mizuta, 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 103206 dpa," J. Nucl. Mater., 283-287, 396-399 (2004).
    • (2004) J. Nucl. Mater , vol.283-287 , pp. 396-399
    • Uehira, A.1    Mizuta, S.2    Ukai, S.3
  • 5
    • 34447580966 scopus 로고    scopus 로고
    • Tensile and transient burst properties of advanced ferritic/martensitic steel claddings after neutron irradiation
    • Y. Yano, T. Yoshitake, S. Yamashita et al., "Tensile and transient burst properties of advanced ferritic/martensitic steel claddings after neutron irradiation," J. Nucl. Mater., 367-370, 127-131 (2007).
    • (2007) J. Nucl. Mater , vol.367-370 , pp. 127-131
    • Yano, Y.1    Yoshitake, T.2    Yamashita, S.3
  • 6
    • 0034264859 scopus 로고    scopus 로고
    • Tensile properties of 11Cr-0.5Mo-2W, V, Nb stainless steel in LMFBR environment
    • A. Uehira, S. Ukai, T. Mizuno et al., "Tensile properties of 11Cr-0.5Mo-2W, V, Nb stainless steel in LMFBR environment," J. Nucl Sci. Technol., 37, 780-786 (2000).
    • (2000) J. Nucl Sci. Technol , vol.37 , pp. 780-786
    • Uehira, A.1    Ukai, S.2    Mizuno, T.3
  • 7
    • 0028259342 scopus 로고    scopus 로고
    • I. Shibahara, T. Omori, Y. Sato et al., Mechanical property degradation of fast reactor fuel cladding during thermal transients, Effects of Radiation on Materials, ASTM STP 1175, 664-678 (1994).
    • I. Shibahara, T. Omori, Y. Sato et al., "Mechanical property degradation of fast reactor fuel cladding during thermal transients," Effects of Radiation on Materials, ASTM STP 1175, 664-678 (1994).
  • 8
    • 38349091895 scopus 로고    scopus 로고
    • S. Nomura, S. Shikakura, S. Ukai et al., Development of long life FBR core materials, Proc. Int. Conf Fast Reactor Related Fuel Cycles, I, 7.4 (1991).
    • S. Nomura, S. Shikakura, S. Ukai et al., "Development of long life FBR core materials," Proc. Int. Conf Fast Reactor Related Fuel Cycles, Vol. I, 7.4 (1991).
  • 10
    • 0442296262 scopus 로고    scopus 로고
    • Characterization of neutron field in the experimental fast reactor for fuel and structural material irradiation test
    • T. Aoyama, T. Sekine, S. Tabuchi, "Characterization of neutron field in the experimental fast reactor for fuel and structural material irradiation test," Nucl. Eng. Des., 228, 21-34 (2004).
    • (2004) Nucl. Eng. Des , vol.228 , pp. 21-34
    • Aoyama, T.1    Sekine, T.2    Tabuchi, S.3
  • 11
    • 0027658697 scopus 로고
    • Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
    • Y. Y. Liu, H. Tsai, M. C. Bilione et al., "Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests," J. Nucl. Mater., 204, 194-202 (1993).
    • (1993) J. Nucl. Mater , vol.204 , pp. 194-202
    • Liu, Y.Y.1    Tsai, H.2    Bilione, M.C.3
  • 12
    • 38349103588 scopus 로고
    • WHC-SA-2513-FP
    • F. H. Huang, "Transient failure behavior of HT9," WHC-SA-2513-FP, 1-14 (1994).
    • (1994) , pp. 1-14
    • Huang, F.H.1
  • 13
    • 38349147267 scopus 로고    scopus 로고
    • N. S. Cannon, F. H. Huang, M. L. Hamilton, Simulated transient behavior of HT9 cladding, Effects of Radiation on Materials, ASTM STP 1046, 729-738 (1990).
    • N. S. Cannon, F. H. Huang, M. L. Hamilton, "Simulated transient behavior of HT9 cladding," Effects of Radiation on Materials, ASTM STP 1046, 729-738 (1990).
  • 14
    • 0042445444 scopus 로고    scopus 로고
    • High-chromium ferritic and martensitic steels for nuclear applications
    • R. L. Klueh, D. R. Harries, "High-chromium ferritic and martensitic steels for nuclear applications," ASTM MONO3 (2001).
    • (2001) ASTM MONO3
    • Klueh, R.L.1    Harries, D.R.2
  • 15
    • 0022225760 scopus 로고
    • Tensile behavior of irradiated 12Cr-1MoVW steel
    • R. L. Klueh, J. M. Vitek, "Tensile behavior of irradiated 12Cr-1MoVW steel," J. Nucl. Mater., 137, 44-50 (1985).
    • (1985) J. Nucl. Mater , vol.137 , pp. 44-50
    • Klueh, R.L.1    Vitek, J.M.2
  • 16
    • 0022062482 scopus 로고
    • Elevated-temperature tensile properties of irradiated 9Cr-1MoVNb steel
    • R. L. Klueh, J. M. Vitek, "Elevated-temperature tensile properties of irradiated 9Cr-1MoVNb steel," J. Nucl. Mater., 132, 27-31 (1985).
    • (1985) J. Nucl. Mater , vol.132 , pp. 27-31
    • Klueh, R.L.1    Vitek, J.M.2
  • 17
    • 0030262413 scopus 로고    scopus 로고
    • Irradiation hardening of reduced activation martensitic steels
    • A. Kimura, T. Morimura, M. Narui et al., "Irradiation hardening of reduced activation martensitic steels," J. Nucl. Mater., 233-237, 319-325 (1996).
    • (1996) J. Nucl. Mater , vol.233-237 , pp. 319-325
    • Kimura, A.1    Morimura, T.2    Narui, M.3
  • 18
    • 0020193995 scopus 로고
    • Chromium-molybdenum steels for fusion reactor first walls - A review
    • R. L. Klueh, "Chromium-molybdenum steels for fusion reactor first walls - A review," Nucl. Eng. Des., 72, 329-344 (1982).
    • (1982) Nucl. Eng. Des , vol.72 , pp. 329-344
    • Klueh, R.L.1
  • 19
    • 0022100950 scopus 로고
    • The development of ferritic steels for fast induced radioactivity decay for fusion reactor applications
    • R. L. Klueh, E. E. Bloom, "The development of ferritic steels for fast induced radioactivity decay for fusion reactor applications," Nucl. Eng. Des./Fusion, 2, 383-389 (1985).
    • (1985) Nucl. Eng. Des./Fusion , vol.2 , pp. 383-389
    • Klueh, R.L.1    Bloom, E.E.2
  • 20
    • 38349123767 scopus 로고    scopus 로고
    • Evaluation of induced activity in a fusion reactor and prospect of advanced low activation blanket structure materials
    • in Japanese
    • T. Noda, "Evaluation of induced activity in a fusion reactor and prospect of advanced low activation blanket structure materials," J. Plasma and Fusion Research, 79, 452-459 (2003) [in Japanese].
    • (2003) J. Plasma and Fusion Research , vol.79 , pp. 452-459
    • Noda, T.1
  • 21
    • 52249118544 scopus 로고    scopus 로고
    • Elevated-temperature ferritic and martensitic steels and their application to future nuclear reactors
    • Nov
    • R. L. Klueh, "Elevated-temperature ferritic and martensitic steels and their application to future nuclear reactors," ORNL/TM-2004/176, Nov. (2004).
    • (2004) ORNL/TM-2004/176
    • Klueh, R.L.1
  • 22
    • 38349127224 scopus 로고    scopus 로고
    • Effects of tungsten on mechanical properties and microstructure in 9Cr-0.5Mo-W steels
    • San Sebastian, Spain, Apr. 27-29
    • H. Naoi, M. Ohgami, Y. Hasegawa et al., "Effects of tungsten on mechanical properties and microstructure in 9Cr-0.5Mo-W steels," Proc. Int. Conf Advanced Heat Resistant Steels for Power Generation, San Sebastian, Spain, Apr. 27-29, 1998, 259-269 (1998).
    • (1998) Proc. Int. Conf Advanced Heat Resistant Steels for Power Generation , pp. 259-269
    • Naoi, H.1    Ohgami, M.2    Hasegawa, Y.3
  • 23
    • 0003501307 scopus 로고    scopus 로고
    • The effect of tungsten on creep properties of high chromium steels for steam turbine
    • San Sebastian, Spain, Apr. 27-29
    • R. Ishii, Y. Tsuda, M. Yamada et al., "The effect of tungsten on creep properties of high chromium steels for steam turbine," Proc. Int. Conf Advanced Heat Resistant Steels for Power Generation, San Sebastian, Spain, Apr. 27-29, 277-287 (1998).
    • (1998) Proc. Int. Conf Advanced Heat Resistant Steels for Power Generation , pp. 277-287
    • Ishii, R.1    Tsuda, Y.2    Yamada, M.3
  • 25
    • 38349185494 scopus 로고    scopus 로고
    • C.-Y. Hsu, D. S. Gelles, T. A. Lechtenberg, Microstructural examination of 12% Cr martensitic stainless steel after irradiation at elevated temperatures in FFTF, Effects of Radiation on Materials, ASTM STP 955, 545-559 (1987).
    • C.-Y. Hsu, D. S. Gelles, T. A. Lechtenberg, "Microstructural examination of 12% Cr martensitic stainless steel after irradiation at elevated temperatures in FFTF," Effects of Radiation on Materials, ASTM STP 955, 545-559 (1987).


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.