메뉴 건너뛰기




Volumn 39-40, Issue , 1998, Pages 575-584

Lifetime and thermal-structural performance of various first wall concepts and implications of creep-fatigue for design and licensing

Author keywords

[No Author keywords available]

Indexed keywords

CREEP; FATIGUE TESTING; LIFE CYCLE; NUCLEAR POWER PLANTS; NUCLEAR REACTOR LICENSING; THERMAL EFFECTS; WATER COOLED REACTORS;

EID: 0032157492     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(97)00162-2     Document Type: Article
Times cited : (5)

References (21)
  • 3
    • 0030181179 scopus 로고    scopus 로고
    • Structural design codes: Strain-life method and fatigue damage estimation for ITER
    • P.J. Karditsas, Structural design codes: strain-life method and fatigue damage estimation for ITER, Fusion Technol. 29 (1996) 615-626.
    • (1996) Fusion Technol. , vol.29 , pp. 615-626
    • Karditsas, P.J.1
  • 4
    • 0029410088 scopus 로고
    • Structural analysis and design against failure of fusion power plant components with special reference to pulsed operation
    • P.J. Karditsas, Structural analysis and design against failure of fusion power plant components with special reference to pulsed operation, Fusion Eng. Des. 30 (1995) 307-323.
    • (1995) Fusion Eng. Des. , vol.30 , pp. 307-323
    • Karditsas, P.J.1
  • 6
    • 0018681825 scopus 로고
    • Stress and lifetime limitations of first wall structural materials
    • C.K. Youngdahl, D.L. Smith, Stress and lifetime limitations of first wall structural materials, J. Nucl. Mater. 85-86 (1979) 153-157.
    • (1979) J. Nucl. Mater. , vol.85-86 , pp. 153-157
    • Youngdahl, C.K.1    Smith, D.L.2
  • 8
    • 0021453361 scopus 로고
    • Comparison of lifetime calculation for fusion reactor first walls based on two creep-fatigue design criteria
    • A.O. Adegbulugbe, Comparison of lifetime calculation for fusion reactor first walls based on two creep-fatigue design criteria, Fusion Eng. Des. 1 (1984) 301-305.
    • (1984) Fusion Eng. Des. , vol.1 , pp. 301-305
    • Adegbulugbe, A.O.1
  • 9
    • 0023385729 scopus 로고
    • Lifetime analysis for fusion reactor first walls and divertor plates
    • T. Horie, S. Tsujimura, A. Minato, T. Tone, Lifetime analysis for fusion reactor first walls and divertor plates, Fusion Eng. Des. 5 (1987) 221-231.
    • (1987) Fusion Eng. Des. , vol.5 , pp. 221-231
    • Horie, T.1    Tsujimura, S.2    Minato, A.3    Tone, T.4
  • 11
    • 0039546303 scopus 로고
    • The mechanical behaviour of newly designed low-activation high chromium martensitic steels
    • E. Dequidt, et al, The mechanical behaviour of newly designed low-activation high chromium martensitic steels, J. Nucl. Mater. 179-181 (1991) 659-662.
    • (1991) J. Nucl. Mater. , vol.179-181 , pp. 659-662
    • Dequidt, E.1
  • 12
    • 0343034806 scopus 로고
    • Lifetime estimation of first wall and blanket structures
    • D. Munz, E. Diegele, Lifetime estimation of first wall and blanket structures, Fusion Eng. Des. 16 (1991) 45-57.
    • (1991) Fusion Eng. Des. , vol.16 , pp. 45-57
    • Munz, D.1    Diegele, E.2
  • 13
    • 0024035646 scopus 로고
    • Irradiation creep and swelling of AISI 316 to exposures of 130 dpa at 385-400°C
    • F.A. Garner, D.L. Porter, Irradiation creep and swelling of AISI 316 to exposures of 130 dpa at 385-400°C, J. Nucl. Mater. 155-157 (1988) 1006-1013.
    • (1988) J. Nucl. Mater. , vol.155-157 , pp. 1006-1013
    • Garner, F.A.1    Porter, D.L.2
  • 14
    • 0019613739 scopus 로고
    • Irradiation creep and interrelation with swelling in austenitic stainless steels
    • K. Ehrlich, Irradiation creep and interrelation with swelling in austenitic stainless steels, J. Nucl. Mater. 100 (1981) 149-166.
    • (1981) J. Nucl. Mater. , vol.100 , pp. 149-166
    • Ehrlich, K.1
  • 15
    • 0021475831 scopus 로고
    • Helium in fusion materials: High temperature embrittlement
    • H. Ullmaier, Helium in fusion materials: High temperature embrittlement, J. Nucl. Mater. 133-134 (1985) 100-104.
    • (1985) J. Nucl. Mater. , vol.133-134 , pp. 100-104
    • Ullmaier, H.1
  • 16
    • 0028494741 scopus 로고
    • Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-IMo to 208 dpa at ∼400°C
    • M.B. Toloczko, et al, Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-IMo to 208 dpa at ∼400°C, J. Nucl. Mater. 212-215 (1994) 604-607.
    • (1994) J. Nucl. Mater. , vol.212-215 , pp. 604-607
    • Toloczko, M.B.1
  • 17
    • 0348138608 scopus 로고
    • Isothermal hold-time tests of structural materials for fusion reactors
    • Karlsruhe, Germany
    • R. Schmitt, W. Scheibe, Isothermal hold-time tests of structural materials for fusion reactors, Proc. 18th SOFT, Karlsruhe, Germany (1994).
    • (1994) Proc. 18th SOFT
    • Schmitt, R.1    Scheibe, W.2
  • 18
    • 0001118239 scopus 로고
    • Low-cycle fatigue properties of the helium implanted 12% Cr steel 1.4914 (MANET)
    • R. Lindau, A. Mosslang, Low-cycle fatigue properties of the helium implanted 12% Cr steel 1.4914 (MANET), J. Nucl. Mater. 179-181 (1991) 753-756.
    • (1991) J. Nucl. Mater. , vol.179-181 , pp. 753-756
    • Lindau, R.1    Mosslang, A.2
  • 19
    • 0000259329 scopus 로고
    • The tensile and fatigue properties of type 1.4914 ferritic steel for fusion reactor applications
    • P. Marmy, et al., The tensile and fatigue properties of type 1.4914 ferritic steel for fusion reactor applications, J. Nucl. Mater. 179-181 (1991) 697-701.
    • (1991) J. Nucl. Mater. , vol.179-181 , pp. 697-701
    • Marmy, P.1
  • 20
    • 0342600592 scopus 로고
    • Santa Monica, California
    • COSMOS/M, Structural Research and Analysis Corporation, FEA system Version 1.70A Santa Monica, California (1994).
    • (1994) FEA System Version 1.70A


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.