메뉴 건너뛰기




Volumn 207, Issue 1, 2001, Pages 21-31

Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions

Author keywords

[No Author keywords available]

Indexed keywords

CODES (SYMBOLS); COMPUTER AIDED DESIGN; FEEDWATER ANALYSIS; STEAM GENERATORS;

EID: 0035400769     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(00)00417-9     Document Type: Article
Times cited : (89)

References (14)
  • 2
    • 0041130246 scopus 로고    scopus 로고
    • CFX AEA, Oxfordshire, UK
    • CFX, 1997. CFX-4.2 Manual. AEA, Oxfordshire, UK.
    • (1997) CFX-4.2 Manual
  • 4
    • 0021497010 scopus 로고
    • Scaling laws for thermal-hydraulic system under single phase and two phase natural circulation
    • Ishii M., Kadaoka I. Scaling laws for thermal-hydraulic system under single phase and two phase natural circulation. Nucl. Eng. Des. 81:1984;411-425.
    • (1984) Nucl. Eng. Des. , vol.81 , pp. 411-425
    • Ishii, M.1    Kadaoka, I.2
  • 5
    • 0342644820 scopus 로고    scopus 로고
    • Development of RETRAN-03/MOV code for thermal-hydraulic analysis of nuclear reactor under moving conditions
    • Kim J.H., Park G.C. Development of RETRAN-03/MOV code for thermal-hydraulic analysis of nuclear reactor under moving conditions. J. Korean Nucl. Soc. 28:(6):1996;542-550.
    • (1996) J. Korean Nucl. Soc. , vol.28 , Issue.6 , pp. 542-550
    • Kim, J.H.1    Park, G.C.2
  • 6
    • 0021410269 scopus 로고
    • Scaling criteria for two-phase flow loops and their application to conceptual 2*4 simulation loop design
    • Kocamustafaogullari G., Ishii M. Scaling criteria for two-phase flow loops and their application to conceptual 2*4 simulation loop design. Nucl. Technol. 65:1984;146-160.
    • (1984) Nucl. Technol. , vol.65 , pp. 146-160
    • Kocamustafaogullari, G.1    Ishii, M.2
  • 8
    • 0342644819 scopus 로고    scopus 로고
    • A study of passive and inherent safety design concepts for advanced light water reactors
    • Korea Atomic Energy Research Institute Report, Korea EPRI Report, Palo Alto, CA
    • Lee, D.J., et al., 1996. A study of passive and inherent safety design concepts for advanced light water reactors. KAERI/CM-112/96, Korea Atomic Energy Research Institute Report, Korea EPRI Report, Palo Alto, CA.
    • (1996) KAERI/CM-112/96
    • Lee, D.J.1
  • 9
    • 0003068316 scopus 로고
    • Study on forced convective heat transfer in curved pipes
    • Mori Y., Nakayama W. Study on forced convective heat transfer in curved pipes. Int. J. Mass Transfer. 10:1967;37-59.
    • (1967) Int. J. Mass Transfer , vol.10 , pp. 37-59
    • Mori, Y.1    Nakayama, W.2
  • 11
    • 50549219736 scopus 로고
    • Prediction of pressure drop during forced circulation boiling of water
    • Thom, J.R.S., 1964. Prediction of pressure drop during forced circulation boiling of water. Int. J. Heat Transfer, 7.
    • (1964) Int. J. Heat Transfer , pp. 7
    • Thom, J.R.S.1
  • 13
    • 0024048564 scopus 로고
    • A movable boundary model for once-through steam generator analysis
    • Tzanos, C.P., 1988. A movable boundary model for once-through steam generator analysis. Nuclear Technology, 82.
    • (1988) Nuclear Technology , pp. 82
    • Tzanos, C.P.1
  • 14
    • 0015475689 scopus 로고
    • Heat transfer from tubes in cross flow
    • Zukauskas A.A. Heat transfer from tubes in cross flow. Adv. Heat Transfer. 8:1972;93-106.
    • (1972) Adv. Heat Transfer , vol.8 , pp. 93-106
    • Zukauskas, A.A.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.