Probabilistic analysis of groundwater and radionuclide transport model from near surface disposal facilities

ABSTRACT

As per the regulatory requirements controlling the disposal of radioactive waste, the performance of waste disposal facilities needs to be assessed quantitatively using predictive models. This estimates the potential impact of disposal on the environment and public health. Near Surface Disposal Facilities (NSDFs), constructed to contain the low level radioactive waste are considered to model the radionuclide migration from the system to the geo-sphere. The radiation dose experienced by an individual through drinking water pathway is the endpoint of assessment of the model. A three dimensional groundwater contaminant transport model with a decaying source is modelled numerically to determine the radiation dose for short-lived and long-lived radionuclides. The consideration of uncertainties constitutes an intrinsic part of modelling. The uncertain input parameters include porosity, longitudinal dispersivity, transverse dispersivity, diffusion coefficient and distribution coefficient. The uncertainty propagation and quantification is carried out using collocation based stochastic response surface method (CSRSM). To run the simulations for the huge set of input, a code is developed using built-in python interface in the numerical model. The results are processed further to obtain the sensitive parameters affecting the output concentrations. Further, the probability of radiation dose exceeding permissible value is estimated by subset simulation.

KEYWORDS:

• Near surface disposal facilities (NSDF)/barrier systems
• numerical modelling (FEFLOW)
• polynomial chaos expansion
• sensitivity analysis
• reliability analysis

View correction statement:

Erratum

Acknowledgements

The authors thank the reviewers for their critical and useful comments.

Disclosure statement

No potential conflict of interest was reported by the authors.

Additional information

Funding

The work presented in this paper is part of research work carried out in the project “Development of probabilistic design and analysis procedures in radioactive waste disposal in NSDF and design of NSDF closure” sponsored by Board of Research in Nuclear Science (BRNS). The discussion with scientists of Bhabha Atomic Research Center (BARC) and their financial assistance is gratefully acknowledged.