THE CONCEPT OF GeRa CODE DEVELOPMENT AND APPLICATION FOR SAFETY STUDIES OF RADIOACTIVE WASTE DISPOSAL SITES
I. V. Kapyrin, S. S. Utkin, Yu. V. Vasilevsky
VANT. Ser.: Mat. Mod. Fiz. Proc 2014. Вып.4. С. 44-54.
In the paper we present the development principles of the GeRa code intended for direct and inverse problem simulations for safe disposal of radioactive waste, i.e. for safety studies of disposal sites and specification of requirements to the waste subject to disposal. The functionality of the code should enable three-dimensional simulations of subsurface flow and migration starting from the development of the subsurface model through the uncertainty quantification and validation. The code will address the tasks of the Russian nuclear industry. In particular, the code is expected to incorporate the features of closed nuclear fuel cycle solutions. In addition to the traditional models of saturated flow and advection-, diffusion- and dispersion-driven transport, the code offers modeling capabilities for thermal and density convection, saturated-unsaturated and multi-phase flow, chemical interactions in the water-rock system (including non-equilibrium conditions). The code is intended for use on three-dimensional unstructured grids and for parallel simulations on supercomputers. The corresponding mathematical models provide for the use of second-order schemes, and advection modeling will be done using low-dissipation schemes. GeRa has a modular structure focused on individual model construction phases. The functionality of each individual module of the code is discussed in detail, including numerical models of physical and chemical processes.Keywords: radioactive waste, disposal safety, three-dimensional modeling, flow, transport, subsurface, parallel simulations, supercomputers.
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