Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지

A Study on the Applicability of MELCOR to Molten Core-Concrete Interaction Under Severe Accidents

  • Published : 2000.10.01
Download PDF
⟨ Previous Next ⟩

Abstract

It has been an essential part for the safety assessment of nuclear power plants to understand various phenomena associated with the molten core-concrete interaction(MCCI) under severe accidents. In this study, the severe accident analysis code MELCOR was used to simulate the MCCI experiments such as SWISS and SURC test series which had been performed in Sandia National Laboratories(SNL). The calculation results were compared with corresponding experimental data such as melt temperature, concrete ablation distance, gas generation rate, and aerosol release rate. Good agreements were observed between MELCOR calculation and experimental data. The melt pool was sustained within the range of high temperature and the concrete ablation occurred continuously. The gas generation and aerosol release were under the influence of melt temperature and overlying water pool, respectively.

Keywords

References

  1. Sandia National Laboratories, MELCOR1.8.3 Computer Code Manuals (1994)
  2. D.R. Bradley and D.R. Gardner, CORCONMOD3: An Integrated Computer Model for Analysis of Molten Core Concrete Interactions, NUREG/CR-5843, (1992)
  3. R.E. Blose, J.E. Gronager, A.J. Suo-Anttila, and J.E. Brockmann, SWISS: Sustained Heated Metallic Melt/Concrete Interactions with Overlying Water Pools, NUREG/CR-4727
  4. E.R. Copus, R.E. Blose, J.E. Brockmann, R.B. Simpson, and D.A. Lucero, Core-Concrete Interactions Using Motlen Urania with Zirconium on a Limestone Concrete Basemat: SURC-1 Experiment, NUREG/CR-5443 (1992)
  5. E.R. Copus, R.E. Blose, J.E. Brockmann, R.D. Gomez, and D.A. Lucero, Core-Concrete Interactions Using Molton Steel with Zirconium on a Basaltic Basemat: SURC-4 Experiment, NUREG/CR-4994 (1989)
  6. J.E. Gronager, A.J. Suo-Antilla, D.R. Bradley, and J.E. Brockmann, TURC1: Large Scale Metallic Melt-Concrete Interaction Experiments and Analysis, NUREG/CR-4420 (1986)
  7. J.E. Gronager, A.J. Suo-Antilla, and J.E. Brockmann, TURC2 AND TURC3: Large Scale UO2/ZrO2/Zr Melt-Concrete Interaction Experiments and Analysis, NUREG/CR-4521 (1986)
  8. M. Corradini and H.H. Reineke, A Review of the BETA Experimental Results and Code Comparison Calculations, Nuclear Science and Engineering, 102, 260-282, (1989)
  9. J.J. Foit, M. Reinmann, B. Adroguer, G. Cenerino, and S. Stiefel, The WECHSL-MOD3 Code: A Computer Program for the Interaction of a Core Melt with Concrete Including the Long Term Behavior. Model Description and User's Manual, FZKA 5416 (1995)
  10. E.R. Copus, Core-Concrete Interaction with Overlying Water Pools, Proceedings of OECD CSNI Specialists Meeting on Core-Debris Concrete Interaction (1992)
  11. M.T. Farmer, MACE Core Coolability Test M1B, 20th Water Reactor Safety Meeting (1992)