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Monte Carlo simulation-based reliability model for the PSA of a radioactive waste repository

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Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
Disposal facilities for radioactive wastes comprise a series of engineered barriers whose purpose is to contain the radionuclides until their radiation hazard has decreased to acceptable levels. In this regard, it is required that the long-term functionality of the system of barriers be evaluated by a quantitative risk analysis procedure, also called performance assessment. In this paper, a Monte Carlo simulation-based reliability model is propounded for the preliminary analysis of the safety performance of a radioactive waste repository, accounting also for barrier degradation processes. The model strengths are: simplicity, chich allows ease of computation, and flexibility, which allows modification to account for various physical aspects and inter-comparison of their effects. An application to a case study of literature is presented to validate the approach and demonstrate its flexibility.
Rocznik
Strony
43--50
Opis fizyczny
Bibliogr. 22 poz., rys., tab., wykr.
Twórcy
autor
  • Politecnico di Milano – Dipartimento di Energia, Milan, Italy
autor
  • Politecnico di Milano – Dipartimento di Energia, Milan, Italy
autor
  • Politecnico di Milano – Dipartimento di Energia, Milan, Italy
  • Ecole Centrale Paris – Supelec, Paris, France
autor
  • ENEA CR Saluggia, Saluggia (VC), Italy
autor
  • ENEA CR Saluggia, Saluggia (VC), Italy
Bibliografia
  • [1] IAEA Safety Standards Series No. WS-G-1.1. (1999). Safety Assessment for Near Surface Disposal of Radioactive Waste. IAEA eds., Vienna.
  • [2] IAEA Safety Standards Series – Requirements, WS-R-1. (1999). Near surface disposal of radioactive waste. IAEA eds., Vienna.
  • [3] Helton, J. C. & Sallaberry, J. C. (2009). Conceptual basis for the definition and calculation of expected dose in performance assessments for the proposed high-level radioactive waste repository at Yucca Mountain, Nevada. Reliability Engineering and System Safety, 94, 677-698.
  • [4] Yim, M.-S. & Simonson, S. A. (2000). Performance assessment models for low level radioactive waste disposal facilities: a review. Progress in Nuclear Energy, 36 (1), 1-38.
  • [5] Swift, P. N., Knowles, K., McNeish, J., Hansen, C. W., Howard, R. L., MacKinnon, R. & Sevougian, S. D. (2008). Yucca mountains 2008 performance assessment: summary. HLRWM 2008, Las Vegas, USA, September 7-11, 575-581.
  • [6] Cadini, F., De Sanctis, J., Girotti, T., Zio, E., Luce, A. & Taglioni, A. (2009). Monte Carlo-based assessment of the safety performance of a radionuclide waste repository. Submitted to Reliability Engineering & System Safety.
  • [7] International Commission on Radiological Protection. (1977). Recommendations of the International Commission on Radiological Protection (ICRP Publication 26). Oxford; New York: Pergamon Press.
  • [8] Nair, R.N. & Krishnamoorthy, T. M. (1999). Probabilistic safety assessment model for near surface radioactive waste disposal facilities. Environmental Modelling & Software, 14, 447-460.
  • [9] Pritzker, A. & Gassman, J. (1980). Application of simplified reliability methods for risk assessment of nuclear waste repository”, Nuclear Technology, 48 (3), 289-297, 1980.
  • [10] Chang, S. H. & Cho, W. J. (1984). Risk analysis of radioactive waste repository based on the time-dependent hazard rate. Radioactive Waste Management and the Nuclear Fuel Cycle, 5 (1), 63-80.
  • [11] Cohen, B. L. (1984). A general probabilistic risk assessment for low level waste burial grounds. Nuclear and Chemical Waste Management, 5 (1), 39-47.
  • [12] Kim, P. O., Cho, W. J. & Chang, S. H. (1988). Probabilistic safety assessment of low-level waste disposal system. Radioactive Waste Management and the Nuclear Fuel Cycle, 10, 253.
  • [13] Kim, Y. N., Kim, J. K. & Kim, T. W. (1993). Risk assessment for shallow land burial of low-level radioactive waste. Waste Management, 13 (8), 589-598.
  • [14] Little, R., Avis, J., Calder, N., Garisto, N., Gierszewski, P., Leung, H., Limer, L., Penfold, J., Towler, G., Walke, R. & Walsh, R. (2009). A preliminary postclosure safety assessment of OPG’s proposed L & ILW deep geologic repository, Canada. Proceedings of the 12th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM’09/DECOM’09, October 11-15, 2009, Liverpool, UK.
  • [15] Seitz, R. R. & Walton, J. C. (1990). Modeling Approaches for Concrete Barriers Used In Low-Level Waste Disposal. NUREG/CR-5542, Idaho National Engineering Laboratory, EG & G Idaho, Inc.
  • [16] Cadini, F., De Sanctis, J., Girotti, T., Zio, E., Luce, A. & Taglioni, A. (2009). Monte Carlo estimation of radionuclide release at a repository scale. Submitted to Annals of Nuclear Energy.
  • [17] Zio, E. (2007). An Introduction to the Basics of Reliability and Risk Analysis. Series In quality, reliability and engineering statistics, Vol. 13, World Scientific Publishing Co. Pte. Ltd., Singapore.
  • [18] Freeze, R. A. & Cherry, J. A. (1979). Groundwater, Prentice Hall Publishing, New Jersey.
  • [19] Internal report ENEA, November 1997.
  • [20] IAEA Series – A safety guide, 111-G-1.1 (1994). Classification of Radioactive Waste. Vienna.
  • [21] IAEA Safety Standards Series – Requirements, WS-R-1 (1999). Near surface disposal of radioactive waste. Vienna.
  • [22] Zio, E., Cadini, F., Avram, D., Girotti, T., Luce, A. & Taglioni, A. (2009). Monte Carlo simulation of a compartment model of radionuclide migration at a radioactive waste repository. Proceedings of the 12th International Conference on EnvironmentalRemediation and Radioactive Waste Management, ICEM’09/DECOM’09, October 11-15, 2009, Liverpool, UK.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-231cfb67-3af0-4e39-85df-377310f81f00
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