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Volumn , Issue , 2004, Pages 1082-1089

Metallographical and numerical investigation of the EC-FOREVER-4 test

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; FINITE ELEMENT METHOD; LIGHT WATER REACTORS; MATHEMATICAL MODELS; MICROSTRUCTURE; NUCLEAR ENERGY; RADIOISOTOPES; REACTOR CORES; THERMAL LOAD;

EID: 14844291610     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (1)

References (11)
  • 3
    • 11344256283 scopus 로고    scopus 로고
    • EC-FOREVER experiments on thermal and mechanical behaviour of a reactor pressure vessel during a severe accident
    • EC-FOREVER-3(B) test. Stockholm, Sweden
    • Giri, A., et al., EC-FOREVER Experiments on Thermal and Mechanical Behaviour of a Reactor Pressure Vessel during a Severe Accident Technical Report. EC-FOREVER-3(B) test. Stockholm, Sweden, 2002.
    • (2002) Technical Report
    • Giri, A.1
  • 8
    • 14844324673 scopus 로고    scopus 로고
    • EC-FOREVER experiments on thermal and mechanical behaviour of a reactor pressure vessel during a severe accident
    • EC-FOREVER-4 test. Stockholm, Sweden
    • B.R. Sehgal, et al., EC-FOREVER Experiments on Thermal and Mechanical Behaviour of a Reactor Pressure Vessel during a Severe Accident. Technical Report. EC-FOREVER-4 test. Stockholm, Sweden, 2002.
    • (2002) Technical Report
    • Sehgal, B.R.1
  • 9
    • 0035438641 scopus 로고    scopus 로고
    • Coupled thermal structural analysis of LWR vessel creep failure experiments
    • Willschütz, H.-G., E. Altstadt, B.R. Sehgal, and F.-P Weiss: Coupled thermal structural analysis of LWR vessel creep failure experiments, Nucl. Eng. Des., vol 208, pp 265-282, 2001.
    • (2001) Nucl. Eng. Des. , vol.208 , pp. 265-282
    • Willschütz, H.-G.1    Altstadt, E.2    Sehgal, B.R.3    Weiss, F.-P.4
  • 10
    • 0037411204 scopus 로고    scopus 로고
    • Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure
    • Willschütz, H.-G, et al., Simulation of Creep Tests with French or German RPV-steel and investigation of a RPV-support against failure, ANNALS OF NUCLEAR ENERGY, vol 30, pp 1033-1063, 2003.
    • (2003) Annals of Nuclear Energy , vol.30 , pp. 1033-1063
    • Willschütz, H.-G.1
  • 11
    • 84933181445 scopus 로고    scopus 로고
    • Post-test calculations of medium scaled pressure vessel creep failure experiments
    • Paper 3200, Córdoba, Spain, May 4-7
    • Willschuetz, H.-G., E. Altstadt, B.R. Sehgal, F.-P. Weiss, Post-Test Calculations of Medium Scaled Pressure Vessel Creep Failure Experiments Proceedings of ICAPP '03, Paper 3200, Córdoba, Spain, May 4-7, 2003.
    • (2003) Proceedings of ICAPP '03
    • Willschuetz, H.-G.1    Altstadt, E.2    Sehgal, B.R.3    Weiss, F.-P.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.