A Coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation

Nuclear Engineering and Design

Volumn 205, Issue 1-2, 2001, Pages 83-90

  Aumiller, D L ^a   Tomlinson, E T ^a   Bauer, R C ^a  

^a BETTIS ATOMIC POWER LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BOUNDARY CONDITIONS; COMPUTATIONAL FLUID DYNAMICS; COMPUTER SOFTWARE; HYDRODYNAMICS; THERMODYNAMICS; TRANSIENTS;

RAPID BLOWDOWN TRANSIENTS;

NUCLEAR REACTOR ACCIDENTS;

EID: 0034818233     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(00)00370-8     Document Type: Article

References (8)

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3. Harwell Laboratory, 1992. FLOW3D Release 3.2: User Manual. AEA Industrial Technology, Oxfordshire, UK.
4. Jeong, J.J., et al., 1997. Assessment of the COBRA/RELAP5 code using the LOFT L2-3 large-break loss-of-coolant experiment. Annals of Nucl. Eng. 24 (14), 1171-1182.
5. Koontz, A.S., Cuta, J.M., 1973. COBRA/TRAC - a thermal-hydraulics code for transient analysis of nuclear reactor vessels and primary coolant systems, NUREG/CR-3046.
6. Lee, S.Y., et al., 1992. COBRA/RELAP5: a merged version of the COBRA-TF and RELAP5/MOD3 codes. Nucl. Tech. 99, 177-187.
7. Martin, R.P., 1995. RELAP5/MOD3 code coupling model. Nucl. Safety 36 (2), 290-299.
8. Smith, K.A., et al., 1995. Coupled RELAPS and CONTAIN accident analysis using PVM. Nucl. Safety 36 (1), 94-108.