Preliminary evaluation of a radioactive waste repository safety performance by a Monte Carlo simulation-based reliability model
-
F. Cadini
Abstract
Disposal facilities are designed to provide long-term isolation of the wastes from the human environment by means of a system of barriers, both engineered and natural. In this regard, it is required that the containment function of the multi-barrier system be evaluated by a quantitative risk analysis procedure, also called performance assessment. This entails the implementation of a Probabilistic Safety Assessment model for representing the stochastic failure behavior of the repository barriers, estimating the release rates of radionuclides into the groundwater stream and the doses from subsequent ingestion of drinking water. To this aim, a Monte Carlo simulation scheme is provided within a reliability modelling approach for the safety performance analysis of a repository, accounting also for barrier degradation processes. An application to a case study of the literature is presented to validate the approach and demonstrate its simplicity and flexibility.
Kurzfassung
Anlagen zur Lagerung radioaktiver Abfälle sind durch ein System von ingenieurtechnischen und natürlichen Barrieren so auszulegen, dass die Langzeitisolierung der Abfälle von der Umwelt gewährleistet ist. In diesem Zusammenhang ist es erforderlich, das die Containment-Funktion des Mehrbarrierensystems mit Hilfe einer quantitativen Risikoanalyse bewertet wird. Dies bedeutet die Einführung eines PSA-Modells, um das stochastische Fehlerverhalten der Endlagerbarrieren darzustellen sowie die Freisetzungsraten der Radionuklide in das Grundwasser und die Dosen infolge der Ingestion des Trinkwasser abzuschätzen. Um dieses Ziel zu erreichen, wird ein Monte Carlo Simulationsprogramm innerhalb eines Zuverlässigkeitsmodells für die sicherheitstechnisch Betrachtung eines Endlagers bereitgestellt, das auch Prozesse der Barriereschwächung berücksichtigt.
References
1 International Atomic Energy Agency (IAEA): Safety Assessment for Near Surface Disposal of Radioactive Waste, Safety Standards Series No. WS-G-1.1, IAEA, Vienna, 1999.Search in Google Scholar
2 International Atomic Energy Agency (IAEA): Near surface disposal of radioactive waste, Safety Standards Series-Requirements No. WS-R-1, IAEA, Vienna, 1999.Search in Google Scholar
3 Helton, J. C.; Sallaberry, J. C.: 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 Safety94 (2009) 677–698.10.1016/j.ress.2008.06.011Search in Google Scholar
4 Yim, M.-S.; Simonson, S. A.: Performance assessment models for low level radioactive waste disposal facilities: a review. Progress in Nuclear Energy36 (2000) 1–38.10.1016/S0149-1970(99)00015-3Search in Google Scholar
5 Swift, P. N.; Knowles, K.; McNeish, J.; Hansen, C. W.; Howard, R. L.; MacKinnon, R.; Sevougian, S. D.: Yucca mountain 2008 performance assessment: summary. HLRWM 2008, Las Vegas, USA, September 7–11, 2008, p. 575–581.Search in Google Scholar
6 Cadini, F.; De Sanctis, J.; Girotti, T.; Zio, E.; Luce, A.; Taglioni, A.: Monte Carlo-based assessment of the safety performance of a radionuclide waste repository. Reliability Engineering&System Safety95 (2009) 859–865.10.1016/j.ress.2010.04.002Search in Google Scholar
7 International Commission on Radiological Protection (ICRP): Recommendations of the International Commission on Radiological Protection. ICRP Publication 26, Annals of the ICRP 1(3), Pergamon Press, Oxford, 1977.Search in Google Scholar
8 Nair, R. N.; Krishnamoorthy, T. M.: Probabilistic safety assessment model for near surface radioactive waste disposal facilities. Environmental Modelling & Software14 (1999) 447–460.10.1016/S1364-8152(98)00090-5Search in Google Scholar
9 Pritzker, A.; Gassman, J.: Application of simplified reliability methods for risk assessment of nuclear waste repository. Nuclear Technology48 (1980) 289–297.Search in Google Scholar
10 Chang, S. H.; Cho, W. J.: Risk analysis of radioactive waste repository based on the time-dependent hazard rate. Radioactive Waste Management and the Nuclear Fuel Cycle5 (1984) 63–80.Search in Google Scholar
11 Cohen, B. L.: A general probabilistic risk assessment for low level waste burial grounds. Nuclear and Chemical Waste Management5 (1984) 39–47.10.1016/0191-815X(84)90006-8Search in Google Scholar
12 Kim, Y. N.; Kim, J. K.; Kim, T. W.: Risk assessment for shallow land burial of low-level radioactive waste. Waste Management13 (1993) 589–598.10.1016/0956-053X(93)90019-SSearch in Google Scholar
13 Little, R.; Avis, J.; Calder, N.; Garisto, N.; Gierszewski, P.; Leung, H.; Limer, L.; Penfold, J.; Towler, G.; Walke, R.; Walsh, R.: A preliminary postclosure safety assessment of OPG's proposed L&ILW deep geologic repository, Canada. Proc of the 12th Int. Conf. on Environmental Remediation and Radioactive Waste Management, ICEM′09/DECOM′09, October 11–15, 2009, Liverpool, UK.10.1115/ICEM2009-16289Search in Google Scholar
14 Seitz, R. R.; Walton, J. C.: Modeling Approaches for Concrete Barriers Used in Low-Level Waste Disposal. NUREG/CR-5542, Idaho National Engineering Laboratory, EG&G Idaho Inc., 1990.Search in Google Scholar
15 Cadini, F.; De Sanctis, J.; Girotti, T.; Zio, E.; Luce, A.; Taglioni, A.: Monte Carlo estimation of radionuclide release at a repository scale. Annals of Nuclear Energy36(6) (2010) 861–866.10.1016/j.anucene.2010.02.011Search in Google Scholar
16 Zio, E.: An Introduction to the Basics of Reliability and Risk Analysis. Series in quality, reliability and engineering statistics. 2007, Vol. 13, World Scientific Publishing Co. Pte. Ltd., Singapore.10.1142/6442Search in Google Scholar
17 Freeze, R. A.; Cherry, J. A.: Groundwater. Prentice Hall Publishing, 1979, New Jersey.Search in Google Scholar
18 International Atomic Energy Agency (IAEA): Classification of Radioactive Waste. Series-A safety guide, No. 111-G-1.1., 1994, Vienna.Search in Google Scholar
19 Zio, E.; Cadini, F.; Avram, D.; Girotti, T.; Luce, A.; Taglioni, A.: Monte Carlo simulation of a compartment model of radionuclide migration at a radioactive waste repository. Proc of the 12th Int. Conf. on Environmental Remediation and Radioactive Waste Management, ICEM′09/DECOM′09, October 11–15, 2009, Liverpool, UK.10.1115/ICEM2009-16168Search in Google Scholar
© 2010, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
- Analyses of loads on reactor pressure vessel internals in a pressurized water reactor due to a loss-of-coolant accident considering fluid-structure interaction
- Preliminary evaluation of a radioactive waste repository safety performance by a Monte Carlo simulation-based reliability model
- Determination of effects of burn up and reflector material on the kinetic parameters for open pool reactor using MCNP code
- Analysis of fuel rod behaviour during limiting RIA in RBMK plants
- Reflection on the ductility of irradiated zircaloy-4 fuel rod cladding
- Prediction, analysis and solution of flow inversion phenomenon in a typical MTR reactor with upward core cooling
- Steam drum process dynamics and level control of a pressure tube BWR
- Nuclear data for cyclotron production of 114mIn/114In and 140Nd/140Pr used in gamma camera monitoring, RIT, ERT and PET
- Effect of thermal gap conductance for MoO3 ampoules irradiated in a high neutron flux
- U1 approximation to the neutron transport equation and calculation of the asymptotic relaxation length
- Application of the TN method to critical slab problem for one-speed neutrons with forward and backward scattering and efficiency of reflection coefficient
- Technical Notes/Technische Mitteilungen
- Rapid preparation of Uranium and Thorium alpha sources by electroplating technique
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
- Analyses of loads on reactor pressure vessel internals in a pressurized water reactor due to a loss-of-coolant accident considering fluid-structure interaction
- Preliminary evaluation of a radioactive waste repository safety performance by a Monte Carlo simulation-based reliability model
- Determination of effects of burn up and reflector material on the kinetic parameters for open pool reactor using MCNP code
- Analysis of fuel rod behaviour during limiting RIA in RBMK plants
- Reflection on the ductility of irradiated zircaloy-4 fuel rod cladding
- Prediction, analysis and solution of flow inversion phenomenon in a typical MTR reactor with upward core cooling
- Steam drum process dynamics and level control of a pressure tube BWR
- Nuclear data for cyclotron production of 114mIn/114In and 140Nd/140Pr used in gamma camera monitoring, RIT, ERT and PET
- Effect of thermal gap conductance for MoO3 ampoules irradiated in a high neutron flux
- U1 approximation to the neutron transport equation and calculation of the asymptotic relaxation length
- Application of the TN method to critical slab problem for one-speed neutrons with forward and backward scattering and efficiency of reflection coefficient
- Technical Notes/Technische Mitteilungen
- Rapid preparation of Uranium and Thorium alpha sources by electroplating technique
