Determination of code accuracy in predicting small-break loca experiment

Nuclear Technology

Volumn 120, Issue 1, 1997, Pages 1-18

  Mavko, Borut ^a,d,e,f   Prošek, Andrej ^a,d,g   D'Auria, Francesco ^b,c  

^a JO EF STEFAN INSTITUTE   (Slovenia)

^b UNIVERSITY OF PISA   (Italy)

^c SAPIENZA UNIVERSITY OF ROME   (Italy)

^d UNIVERSITY OF LJUBLJANA   (Slovenia)

^e GEORGIA INSTITUTE OF TECHNOLOGY   (United States)

^f UNIVERSITY OF MARIBOR   (Slovenia)

^g Reactor Engineering Division

Author keywords

Code accuracy; IAEA SPE 4 experiment; Thermal hydraulic codes

Indexed keywords

CALCULATIONS; COMPUTER SOFTWARE; ERROR CORRECTION; FAST FOURIER TRANSFORMS; REACTOR CORES; TRANSIENTS;

CORE DRYOUT;

LOSS OF COOLANT ACCIDENTS;

EID: 0031245970     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT97-A35427     Document Type: Article

References (22)

1. F. D'AURIA, M. LEONARDI, and R. POCHARD, "Methodology for the Evaluation of Thermal-Hydraulic Codes Accuracy," Proc. Int. Conf. New Trends in Nuclear System Thermohydraulics, Pisa, Italy, 1994, p. 467 (1994).
2. "CSNI International Standard Problem N.21 - Comparison Report Vols. 1 and 2," OECD-CSNI 162, Organization for Economic Cooperation and Development Committee on the Safety of Nuclear Installations (1989).
3. W. AMBROSINI, M. P. BREGHI, and F. D'AURIA, "Evaluation of Code Accuracy in the Prediction of the OECD/CSNI ISP 22," DCMN-NT 176 (91), University of Pisa (1991).
4. H. PURHONEN, J. KOUHIA, and H. HOLMSTRÖM, "OECD/CSNI International Standard Problem No. 33 - Comparison Report," NEA/CSNI/R(94)24, Nuclear Energy Agency (1994).
5. F. D'AURIA, F. ORIOLO, M. LEONARDI, and S. PACI, "Code Accuracy Evaluation of ISP35 Calculations Based on NUPEC M-7-1 Test," Proc. 2nd Regional Mtg. Nuclear Energy in Central Europe, Portorož, Slovenia, September 11-14, 1995, p. 516, Nuclear Society of Slovenia (1995).
6. A. PROŠEK, I. PARZER, B. MAVKO, M. FROGHERI, F. D'AURIA, and M. LEONARDI, "Application of the FFT Method to an IAEA-SPE-4 Experiment Simulation," Proc. Annual Mtg. Nuclear Technology '95, Nürnberg, Germany, May 16-18, p. 115, INFORUM Verlags- und Verwaltungsgesellschaft (1995).
7. F. D'AURIA, A. ERAMO, M. FROGHERI, and G. M. GALASSI, "Accuracy Quantification in SPE-1 to SPE-4 Organised by IAEA," Proc. 4th Int. Conf. Nuclear Engineering ICONE-4, New Orleans, Louisiana, March 10-14, 1996, Vol. 3, p. 461, American Society of Mechanical Engineers and Japan Society of Mechanical Engineers (1996).
8. "CSNI Code Validation Matrix of Thermalhydraulic Codes for LWR LOCA and Transient," CSNI 132, Committee on the Safety of Nuclear Installations (1987).
9. H. HOLMSTRÖM, "Quantification of Code Uncertainties," presented at Specialists' Mtg. Committee on the Safety of Nuclear Installations Transient Two-Phase Flow - System Thermalhydraulics, Aix-En-Provence, France, April 6-8, 1992.
10. R. R. SCHULTZ, "Methodology for Quantifying Calculational Capability of RELAP5/MOD3 Code for SBLOCAs, LBLOCAs and Operational Transients," presented at Mtg. First Code Assessment and Maintenance Program, Villigen, Switzerland, June 24-26, 1992.
11. R. BOVALINI, F. D'AURIA, and M. LEONARDI, "Qualification of the Fast Fourier Transform Based Methodology for the Quantification of Thermalhydraulic Code Accuracy," DCMN-NT 194 (92), University of Pisa (1992).
12. G. ÉZSÖL and L. SZABADOS, "IAEA SPE-4: Pre-Test Results of the 4th IAEA PMK-2 Standard Problem Exercise," KFKI Atomic Energy Research Institute (1994).
13. L. SZABADOS, G. BARANYAI, F. BAUMANN, M. DUS, G. ÉZSÖL, MAROTI, I. NAGY, L. PERNECZKY, and P. WINDBERG, "IAEA-SPE-4 Specification for the Fourth IAEA Standard Problem Exercise," KFKI Atomic Energy Research Institute (1993).
14. A. PROŠEK, I. PARZER, B. MAVKO, M. FROGHERI, F. D'AURIA, and M. LEONARDI, "Assessment of IAEA-SPE-4 Calculations Using FFT Method," IJS-DP-7252, Jožef Stefan Institute (1995).
15. P. P. CEBULL and Y. A. HASSAN, "Simulation of the IAEA's Fourth Standard Problem Exercise Small-Break Loss-of-Coolant Accident Using RELAP5/MOD3.1," Nucl. Technol., 109, 327 (1995).
16. "Simulation of a Loss of Coolant Accident Without High Pressure Injection but with Secondary Side Bleed and Feed," IAEA-TECDOC-848, International Atomic Energy Agency (1995).
17. "Simulation of Beyond Design Basis Accident with Bleed and Feed Preventive Measures," IAEA-TECDOC, DRAFT, International Atomic Energy Agency (1994).
18. S. N. AKSAN, F. D'AURIA, and H. STAEDTKE, "User Effects on the Thermalhydraulic Transient System Code Calculations," J. Nucl. Eng. Des., 145, 159 (1993).
19. A. PROŠEK and B. MAVKO, "Application of Qualitative Analysis to IAEA-SPE-4 Calculations," Proc. 3rd Regional Mtg.: Nuclear Energy in Central Europe, Portorož, Slovenia, September 16-19, 1996, p. 246, Nuclear Society of Slovenia (1996).
20. A. PROŠEK and B. MAVKO, "Qualitative Analysis of IAEA-SPE-4 Calculation," IJS-DP-7406, Jožef Stefan Institute (1996).
21. W. AMBROSINI, F. D'AURIA, and G. M. GALASSI, "Boundary Conditions and Uncertainty Evaluations in System Thermalhydraulics," Proc. Nat. Conf. Transmissone del calore, Universita di L'Aquila, Italy, June 23-24, 1994, p. 505 (1994).
22. "Simulation of a Loss of Coolant Accident with Rupture in the Steam Generator Hot Collector," IAEA-TECDOC-586, International Atomic Energy Agency (1991).