Use of coupled code technique for Best Estimate safety analysis of nuclear power plants

Progress in Nuclear Energy

Volumn 49, Issue 1, 2007, Pages 1-13

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

^a UNIVERSITY OF PISA   (Italy)

Author keywords

Best Estimate tools; Coupled code technique; Nuclear safety analysis

Indexed keywords

INDUSTRIAL ECONOMICS; LIGHT WATER REACTORS; NUCLEAR REACTOR ACCIDENTS;

BEST ESTIMATE TOOLS; COUPLED CODE TECHNIQUES; NUCLEAR SAFETY ANALYSIS; SPACE-DEPENDENT POWER GENERATION;

NUCLEAR POWER PLANTS;

EID: 33845657364     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2006.10.002     Document Type: Review

References (18)

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 (1993) 1-2
2. Bousbia Salah, A., 2004. Overview of coupled system thermal-hydraulic-3D neutron kinetics code applications. Ph.D Thesis (Ref: 17033), Università di Pisa.
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., and D'Auria F. Peach Bottom Cycle 2 low flow stability tests analysis using RELAP5/PARCS. Annals of Nuclear Energy 33 (2006) 646-652
5. Bousbia Salah A., Vedovi J., D'Auria F., Galassi G.M., and Ivanov K. Analysis of the OECD/DOE/CEA VVER1000 CT-1 benchmark using the coupled RELAP5/PARCS codes. Progress in Nuclear Energy 48 8 (2006) 806-819
6. Carmichael, L.A., Niemi, R.O., 1978. Transient and stability tests at Peach Bottom Atomic Power Station Unit 2 at end of cycle 2 (EPRI NP-564).
7. D'Auria, F., 1997. State of the art report on boiling water reactor stability (OECD/NEA/CSNI OECD/GD (97) 13).
8. D'Auria F., and Galassi G.M. Code validation and uncertainties in system thermal-hydraulics. Progress in Nuclear Energy 33 (1998) 175
9. D'Auria F., and Giannotti W. Development of code with capability of internal assessment of uncertainty. Nuclear Technology 131 1 (2000) 159
10. D'Auria, F., (Lead Author) (2004). Neutronics/thermal-hydraulics coupling in LWR technology: state-of-the-art report (REAC-SOAR). CRISSUE-S-WP2. (OCDE/NEA-5436).
11. Ivanov K., Beam T., Baratta A., Irani A., and Trikouros N. PWR MSLB Benchmark. Volume 1: Final Specifications (1999) (NEA/NSC/DOC(99)8)
12. Ivanov B., and Ivanov K. VVER-1000 Coolant Transient Benchmark: Phase-1 (V1000CT-1). Volume I: Final Specifications (2002) (OECD Paris, NEA/NSC/DOC)
13. 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).
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. Petruzzi A., D'Auria F., Giannotti W., and Ivanov K. Methodology of internal assessment of uncertainty and extension to neutron kinetics/thermal-hydraulics coupled codes. Nuclear Science and Engineering 149 2 (2005) 211-236
16. Ransom, V.H., Wagner, R.J., Trapp, J.A., Johnsen, G.W., Miller, C.S., Kiser, D.M., Riemke, R.A., 1990. RELAP5/MOD3: Code manual: user guide and input requirements (NUREG/CR-4312 EGG-2396).
17. Solis, J., Ivanov, K., Sarikaya, B., Olson, A., Hunt, K.W., 2001. Boiling water reactor Turbine Trip (TT) benchmark. Volume 1: final specifications (NEA/NSC/DOC).
18. Trambauer, K., 1997. Computer and compiler effects on code results report. OECD/CSNI Report (OCDE/GD(97) 6).