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Volumn 235, Issue 16, 2005, Pages 1727-1736

Assessment study of the coupled code RELAP5/PARCS against the Peach Bottom BWR turbine trip test

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; CODES (SYMBOLS); COMPUTATIONAL METHODS; COMPUTER SIMULATION; CORRELATION METHODS; HEAT TRANSFER COEFFICIENTS; MATHEMATICAL MODELS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; NUSSELT NUMBER; SENSITIVITY ANALYSIS; THREE DIMENSIONAL; TURBINES;

EID: 20444459538     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.02.019     Document Type: Article
Times cited : (8)

References (20)
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    • (1993) Nucl. Eng. Des. , vol.145 , pp. 159-174
    • Aksan, S.N.1    D'Auria, F.2    Staedtke, H.3
  • 3
    • 1842542108 scopus 로고    scopus 로고
    • Analysis of the Peach Bottom 2 BWR turbine trip experiment by RELAP5/Mod3.2
    • A. Bousbia Salah, and F. D'Auria Analysis of the Peach Bottom 2 BWR turbine trip experiment by RELAP5/Mod3.2 J. Nucl. Tech. Radiol. Prot. XVII 2002 44 49
    • (2002) J. Nucl. Tech. Radiol. Prot. , vol.17 , pp. 44-49
    • Bousbia Salah, A.1    D'Auria, F.2
  • 5
    • 1842611120 scopus 로고    scopus 로고
    • Sensitivity analysis of the Peach Bottom turbine trip 2 experiment
    • A. Bousbia Salah, F. D'Auria, and M. Bambara Sensitivity analysis of the Peach Bottom turbine trip 2 experiment Kerntechnik 69 2004 1 8
    • (2004) Kerntechnik , vol.69 , pp. 1-8
    • Bousbia Salah, A.1    D'Auria, F.2    Bambara, M.3
  • 7
    • 20444470208 scopus 로고    scopus 로고
    • Validation of accident and safety analysis methodology
    • Vienna
    • D'Auria, F., Fischer, K., Mavko, B., Sartmandjiev, A. (Lead Authors), 2001. Validation of Accident and Safety Analysis Methodology. IAEA Report CRP/J.020.03, Vienna.
    • (2001) IAEA Report , vol.CRP-J.020.03
    • D'Auria, F.1    Fischer, K.2    Mavko, B.3    Sartmandjiev, A.4
  • 8
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    • Revisiting critical issues in nuclear reactor design/safety by using 3-D neutronics/thermalhydraulics models: State-of-the-report (CRISSUE-S)
    • EC Luxembourg, 10-13 November
    • D'Auria, F. (Lead Author), 2003. Revisiting Critical Issues in Nuclear Reactor Design/Safety by Using 3-D Neutronics/Thermalhydraulics Models: State-of-the-Report (CRISSUE-S). FISA-2003/EU Research in Reactor Safety, EC Luxembourg, 10-13 November.
    • (2003) FISA-2003/EU Research in Reactor Safety
    • D'Auria, F.1
  • 9
    • 20444433090 scopus 로고
    • A fuel assembly burnup program
    • CASMO-3 STUDSVIK/NFA-89/3
    • Edenius, M., Forssen, B., 1989. CASMO-3, A Fuel Assembly Burnup Program, Users Manual. STUDSVIK/NFA-89/3.
    • (1989) Users Manual
    • Edenius, M.1    Forssen, B.2
  • 10
    • 0003506282 scopus 로고
    • RELAP5/MOD3 code manual
    • Idaho National Engineering Laboratory, Idaho Falls, Idaho, NUREG/CR-5536, INEL-95/0174
    • Fletcher, C.D., Schultz, R.R., 1995. RELAP5/MOD3 Code Manual, vol. IV, User's Guidelines. Idaho National Engineering Laboratory, Idaho Falls, Idaho, NUREG/CR-5536, INEL-95/0174.
    • (1995) User's Guidelines , vol.4
    • Fletcher, C.D.1    Schultz, R.R.2
  • 11
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    • Progress in development and use of coupled codes for accident analysis
    • 26-28 November in press
    • IAEA TECDOC. Progress in Development and Use of Coupled Codes for Accident Analysis. Summary Report of a Technical Meeting held in IAEA Vienna, 26-28 November 2003, in press.
    • (2003) Summary Report of a Technical Meeting Held in IAEa Vienna
  • 13
    • 0037395896 scopus 로고    scopus 로고
    • Modeling of low-pressure subcooled flow boiling using the RELAP5 code
    • B. Končar, and B. Mavko Modeling of low-pressure subcooled flow boiling using the RELAP5 code Nucl. Eng. Des. 220 2003 255 273
    • (2003) Nucl. Eng. Des. , vol.220 , pp. 255-273
    • Končar, B.1    Mavko, B.2
  • 17
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  • 18
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  • 19
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  • 20
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.