Published 1990 | Version v1
Book

Sensitivity analysis of radionuclide transport model using the Differential Algebra method

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

The technique of sensitivity analysis is necessary for the performance assessment of the waste repositories and validation of models to determine key parameters in the models. Because, the parameters of the models describe physical and chemical processes in geologic conditions are generally not well known. An automated procedure is developed for performing large-scale sensitivity studies based on the use of computer tools. The procedure is composed of a FORTRAN precompilar called SANA and a preprocessor called PRESANA. The SANA code translates a FORTRAN code into its sensitivity analysis code using the Differential Algebra method, and the PRESANA is the computer tool to help the translation of FORTRAN code. In this presentation, we describe the automated procedure of sensitivity analysis and its application to the radionuclide transport codes, and discuss the applicability of SANA and PRESANA codes. The UCB-NE-10.3 and Finite Element codes developed to simulate the migration of radionuclides in groundwater were chosen as the targets of this procedure. (author)

Additional details

Publishing Information

Publisher
Nuclear Energy Data Center.
Imprint Place
Tokai, Ibaraki (Japan)
Imprint Title
Proceedings of the first international conference on supercomputing in nuclear applications (SNA '90)
Imprint Pagination
689 p.
Journal Page Range
p. 233-238.

Conference

Title
1. international conference on supercomputing in nuclear applications.
Dates
12-16 Mar 1990.
Place
Mito City (Japan).