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Volumn 75, Issue 15, 1998, Pages 1055-1064

Deterministic assessment of reactor pressure vessel integrity under pressurised thermal shock

Author keywords

Crack; Deterministic integrity assessment; Finite element method; Fracture toughness; Nil ductility transition temperature; Pressurised thermal shock; Reactor pressure vessel; Stress intensity factor

Indexed keywords

CRACK INITIATION; CRACK PROPAGATION; DUCTILITY; FINITE ELEMENT METHOD; FRACTURE TOUGHNESS; LOSS OF COOLANT ACCIDENTS; MATHEMATICAL MODELS; NUCLEAR REACTORS; STRESS INTENSITY FACTORS; THERMAL STRESS;

EID: 0032432599     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0308-0161(98)00109-4     Document Type: Article
Times cited : (11)

References (11)
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  • 3
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    • Fracture mechanical assessment of cracks under cyclic thermal shock and operational conditions
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    • Krolop, S.1    Pfeffer, P.2    Stegmeyer, R.3
  • 5
    • 38249000295 scopus 로고
    • Fracture mechanics investigations on cylindrical large-scale specimens under thermal shock loading
    • Stumpfrock L., Ross E., Huber H., Weber U. Fracture mechanics investigations on cylindrical large-scale specimens under thermal shock loading. Nucl. Engng. Design. 144:1993;31-44.
    • (1993) Nucl. Engng. Design. , vol.144 , pp. 31-44
    • Stumpfrock, L.1    Ross, E.2    Huber, H.3    Weber, U.4
  • 6
    • 0041796880 scopus 로고
    • Comparative analyses concerning integrity of VVER-440 reactor pressure vessels
    • Sievers J., Liu X., Rajamaki P., Talja H., Raiko H. Comparative analyses concerning integrity of VVER-440 reactor pressure vessels. Nucl. Engng. Design. 159:1995;63-68.
    • (1995) Nucl. Engng. Design. , vol.159 , pp. 63-68
    • Sievers, J.1    Liu, X.2    Rajamaki, P.3    Talja, H.4    Raiko, H.5
  • 8
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    • Parametric studies in the frame work of RPV integrity assessment
    • Liu X., Sievers J. Parametric studies in the frame work of RPV integrity assessment. Structural Mechanics in Reactor Technology. 14:(G02/5):1997;67-75.
    • (1997) Structural Mechanics in Reactor Technology , vol.14 , Issue.G02-5 , pp. 67-75
    • Liu, X.1    Sievers, J.2
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  • 10
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    • Review of limit loads of structures containing defects
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    • Miller, A.G.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.