메뉴 건너뛰기




Volumn 1329, Issue , 1998, Pages 298-327

Developing fracture assessment methods for fusion reactor materials with small specimens

Author keywords

Confocal microscopy; Fracture; Fracture reconstruction; Fracture toughness; Fusion materials; Micromechanics

Indexed keywords

COMPUTER SIMULATION; CRACKS; FINITE ELEMENT METHOD; FRACTURE TESTING; FUSION REACTORS; MATHEMATICAL MODELS; STEEL TESTING; STRAIN RATE; TENSILE PROPERTIES; THERMAL EFFECTS; VANADIUM ALLOYS; YIELD STRESS;

EID: 0032230507     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp37997s     Document Type: Article
Times cited : (33)

References (30)
  • 3
    • 0019602712 scopus 로고
    • Relationship between J-Integral and Crack Opening Displacement for Stationary and Extending Cracks
    • Shih, C. F., "Relationship Between J-Integral and Crack Opening Displacement for Stationary and Extending Cracks," Journal of Mechanics and Physics of Solids, Vol. 29 (1981) p. 305.
    • (1981) Journal of Mechanics and Physics of Solids , vol.29 , pp. 305
    • Shih, C.F.1
  • 5
    • 0027627221 scopus 로고
    • J and CTOD Estimation Equations for Shallow Cracks in Single Edge Notch Bend Specimens
    • Kirk, M. T. and Dodds, R. H., "J and CTOD Estimation Equations for Shallow Cracks in Single Edge Notch Bend Specimens," Journal of Testing and Evaluation, Vol. 24, No. 4. (1993) p.2 28.
    • (1993) Journal of Testing and Evaluation , vol.24 , Issue.4 , pp. 2-28
    • Kirk, M.T.1    Dodds, R.H.2
  • 8
    • 0028496518 scopus 로고
    • On the Ductile to Brittle Transition in Martensitic Stainless Steels
    • Odette, G. R., "On the Ductile to Brittle Transition in Martensitic Stainless Steels", Journal of Nuclear Materials, Vols. 212-215 (1994) p. 45.
    • (1994) Journal of Nuclear Materials , vol.212-215 , pp. 45
    • Odette, G.R.1
  • 11
    • 0343072935 scopus 로고
    • Code of Federal Regulations, Chapter 10, Part 50, U. S. Government Printing Office, Washington, D. C.
    • Code of Federal Regulations, Chapter 10, Part 50, "Domestic Licensing of Production and Utilization Facilities," U. S. Government Printing Office, Washington, D. C., 1988.
    • (1988) Domestic Licensing of Production and Utilization Facilities
  • 12
    • 0004121095 scopus 로고
    • Section III, Nuclear Power Plant Components, Division 1, New York
    • American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Nuclear Power Plant Components, Division 1, New York, 1986.
    • (1986) ASME Boiler and Pressure Vessel Code
  • 14
    • 0021139509 scopus 로고
    • The Scatter in KIc Results
    • Wallin, K., "The Scatter in KIc Results", Engineering Fracture Mechanics, Vol. 19-6 (1984) p. 1085
    • (1984) Engineering Fracture Mechanics , vol.19 , Issue.6 , pp. 1085
    • Wallin, K.1
  • 15
    • 0029632032 scopus 로고
    • A Perspective on Transition Temperature and KIc Data Characterization
    • ASTM STP 1207, American Society for Testing and Materials
    • McCabe, D., Merkle, J. G., Nanstad, R., "A Perspective on Transition Temperature and KIc Data Characterization", Fracture Mechanics, 24, ASTM STP 1207, American Society for Testing and Materials (1994) p. 215.
    • (1994) Fracture Mechanics , vol.24 , pp. 215
    • McCabe, D.1    Merkle, J.G.2    Nanstad, R.3
  • 24
    • 0030218454 scopus 로고    scopus 로고
    • On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels
    • ASTM STP 1270, American Society for Testing and Materials
    • Lucas, G. E., Odette, G. R., Sheckherd, J. W., Edsinger, K., Wirth, B., "On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels", Effects of Radiation on Materials, 17, ASTM STP 1270, American Society for Testing and Materials (1996) p. 790.
    • (1996) Effects of Radiation on Materials , vol.17 , pp. 790
    • Lucas, G.E.1    Odette, G.R.2    Sheckherd, J.W.3    Edsinger, K.4    Wirth, B.5
  • 27
    • 0030217375 scopus 로고    scopus 로고
    • Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction
    • ASTM STP 1270, American Society for Testing and Materials
    • Wirth, B., Edsinger, K., Odette, G. R., Lucas, G. E., "Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction", Effects of Radiation on Materials, 17, ASTM STP 1270, American Society for Testing and Materials (1996) p. 706.
    • (1996) Effects of Radiation on Materials , vol.17 , pp. 706
    • Wirth, B.1    Edsinger, K.2    Odette, G.R.3    Lucas, G.E.4
  • 28
    • 0342638706 scopus 로고    scopus 로고
    • An Integrated Approach to Developing a Data Base and Physically-Based Methods for Assessing the Fracture Limits of Fusion Reactor Structures
    • submitted to
    • Odette, G. R. and Lucas, G. E., "An Integrated Approach to Developing a Data Base and Physically-Based Methods for Assessing the Fracture Limits of Fusion Reactor Structures," submitted to Journal of Nuclear Materials.
    • Journal of Nuclear Materials
    • Odette, G.R.1    Lucas, G.E.2
  • 29
    • 0000169357 scopus 로고
    • The Relation between Irradiation Hardening and Embrittlement
    • ASTM-STP-870, American Society for Testing and Materials
    • Odette, G.R., Lombrozo, P.M., and Wullaert, R.A., "The Relation Between Irradiation Hardening and Embrittlement," Effects of Irradiation on Materials, ASTM-STP-870, American Society for Testing and Materials (1985) p. 841.
    • (1985) Effects of Irradiation on Materials , pp. 841
    • Odette, G.R.1    Lombrozo, P.M.2    Wullaert, R.A.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.