Application of coulped code method for the analysis of VVER-1000 coolant transient benchmark

Progress in Nuclear Energy

Volumn 51, Issue 1, 2009, Pages 146-154

  Salah, Anis Bousbia ^a   D'Auria, Francesco ^a  

^a UNIVERSITY OF PISA   (Italy)

Author keywords

Best estimate tools; Coupled code technique; Nuclear safety analysis

Indexed keywords

APPLICATIONS; BENCHMARKING; OPTIMIZATION;

ACCIDENT SCENARIOS; BEST-ESTIMATE TOOLS; COMPUTATIONAL TOOLS; COMPUTER TECHNOLOGIES; CORE NEUTRONICS; CORE PERFORMANCES; COUPLED CODE TECHNIQUE; COUPLED CODES; DESIGN OPTIMIZATIONS; LOCAL SPACES; MATURITY LEVELS; NEW GENERATIONS; NUCLEAR SAFETY ANALYSIS; PRIMARY CIRCUITS; SAFETY EVALUATIONS; STRONG COUPLINGS; TO SWITCHES; TRANSIENT EVENTS; TYPICAL APPLICATIONS;

CODES (SYMBOLS);

EID: 56949104484     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2008.02.005     Document Type: Article

References (16)

1. Aksan S.N., D'Auria F., and Staedtke H. User effects on the thermal-hydraulic transient system codes calculations. Nuclear Engineering and Design 145 1 and 2 (1993) 159-174
2. Aumiller D.L., Tomlinson E.T., and Bauer R.C. A coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation. Nuclear Engineering and Design 205 (2001) 83-90
3. Bousbia Salah A., Kliem S., Rohde U., D'Auria F., and Petruzzi A. Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code. Nuclear Engineering and Design 236 (2006) 1240-1255
4. Bousbia Salah A., Parisi C., D.Auria F., 2006b. Analysis of the OECD/DOE/CEA VER1000 CT-2 benchmark Ex. 2 by RELAP5-PARCS coupled codes, OECD/DOE/CEA VVER-1000 coolant transient benchmark - fourth workshop (V1000-CT4), Pisa, Italy, April 24-25, 2006.
5. Bousbia Salah A., and D'Auria F. Use of coupled code technique for best estimate safety analysis of nuclear power plants. Progress in Nuclear Energy 49 (2007) 1-13
6. D'Auria F., and Galassi G.M. Code validation and uncertainties in system thermal-hydraulics. Progress in Nuclear Energy 33 (1998) 175-216
7. D'Auria, F., Bousbia Salah, A., Galassi, G.M., Vedovi, J., Reventós, F., Cuadra, A., Gago, J.L., Sjöberg, A., Yitbarek, M., Sandervåg, O., Garis, N., Anhert, C., Aragonés, J.M., Verdù, G., Mirò, R., Hadek, J., Macek, J., Ivanov, K., Uddin, R., Sartori, E., Rindelhardt, U., Rohde, U., Frid, W., Panayotov, D., 2004. Neutronics/thermal-hydraulics coupling in LWR technology: state-of-the-art report (REAC-SOAR). CRISSUE-S-WP2, OCDE/NEA-5436.
8. D'Auria F., Bousnbia-Salah A., Petruzzi A., and Del Nevo A. State of the art in using best estimate calculation tools in nuclear technology. Nuclear Engineering and Technology 38 N.1 (2006) 11-32
9. D'Auria F., and Giannotti W. Development of code with capability of internal assessment of uncertainty. Nuclear Technology 131 1 (2000) 159
10. Ivanov K., Olson A., and Sartori E. OECD/NRC BWR turbine trip transient benchmark as a basis for comprehensive qualification and studying best-estimate coupled codes. Nuclear Science and Engineering 148 2 (2004) 195-207
11. Ivanov K., and Avramova M. Challenges in coupled thermal-hydraulics and neutronics simulations for LWR safety analysis. Annals of Nuclear Energy 34 (2007) 501-513
12. Joo, H.G., Barber, D., Jiang, G., Downar, T.J., 1998. PARCS, a multi-dimensional two group reactor kinetics code based on the nonlinear analytic nodal method. PU/NE-98-26.
13. Kolev, N., Petrov, N., Donov, J., Angelova, D., Aniel, S., Royer, E., Ivanov, B., Ivanov, K., Lukanov, E., Dinkov, Y, Popov, D., Nikonov, S., 2006. VVER-1000 coolant transient benchmark phase 2 (V1000CT-2). Vol. II: MSLB problem - final specifications, NEA/NSC/DOC(2006)6.
14. Langenbuch S., Krzykacz-Hausmann B., Schmidt K.D., Hegyi G., Kereszturi A., Kliem S., Hadek J., Danilin S., Nikonov S., Kuchin A., Khalimanchuk V., and Hamalainen A. Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients. Nuclear Engineering and Design 235 (2005) 521-540
15. Stamm'ler R.J., and Abbate M.J. Methods of Steady-State Reactor Physics in Nuclear Design (1983), Academic Press
16. Yadigaroglu G. Computational fluid dynamics for nuclear applications: from CFD to multi-scale CMFD. Nuclear Engineering and Design 235 (2005) 153-164