23
Views
12
CrossRef citations to date
0
Altmetric
Technical Paper

Determination of Code Accuracy in Predicting Small-Break LOCA Experiment

, &
Pages 1-18 | Published online: 12 May 2017

References

  • 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).
  • “CSNI International Standard Problem N.21—Comparison Report Vols. 1 and 2,” OECD-CSNI162, Organization for Economic Cooperation and Development Committee on the Safety of Nuclear Installations (1989).
  • 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).
  • 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).
  • 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, Portoroz, Slovenia, September 11–14, 1995, p. 516, Nuclear Society of Slovenia (1995).
  • A. PROSEK, 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).
  • 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).
  • “CSNI Code Validation Matrix of Thermalhydraulic Codes for LWR LOCA and Transient,” CSNI 132, Committee on the Safety of Nuclear Installations (1987).
  • 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.
  • 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.
  • 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).
  • G. EZSÖL and L. SZABADOS, “IAEA SPE-4: Pre-Test Results of the 4th IAEA PMK-2 Standard Problem Exercise”, KFKI Atomic Energy Research Institute (1994).
  • L. SZABADOS, G. BARANYAI, F. BAUMANN, M. DUS, G. EZSÖL, A. MAROTI, I. NAGY, L. PERNECZKY, and P. WTNDBERG, “IAEA-SPE-4 Specification for the Fourth IAEA Standard Problem Exercise”, KFKI Atomic Energy Research Institute (1993).
  • A. PROSEK, I. PARZER, B. MAVKO, M. FROGHERI, F. D’AURIA, and M. LEONARDI, “Assessment of IAEA-SPE-4 Calculations Using FFT Method”, IJS-DP-7252, Jozef Stefan Institute (1995).
  • 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).
  • “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).
  • “Simulation of Beyond Design Basis Accident with Bleed and Feed Preventive Measures,” IAEA-TECDOC, DRAFT, International Atomic Energy Agency (1994).
  • 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).
  • A. PROSEK and B. MAVKO, “Application of Qualitative Analysis to IAEA-SPE-4 Calculations,” Proc. 3rd Regional Mtg.: Nuclear Energy in Central Europe, Portoroz, Slovenia, September 16–19, 1996, p. 246, Nuclear Society of Slovenia (1996).
  • A. PROSEK and B. MAVKO, “Qualitative Analysis of IAEA-SPE-4 Calculation”, US-DP-7406, Jozef Stefan Institute (1996).
  • 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).
  • “Simulation of a Loss of Coolant Accident with Rupture in the Steam Generator Hot Collector,” IAEA-TECDOC-586, International Atomic Energy Agency (1991).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.