Sensitivity analysis using computer calculus: A nuclear waste isolation application
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:7198375
An automated procedure for performing large-scale sensitivity studies based on the use of computer calculus is presented. The procedure is embodied in a FORTRAN precompiler called GRESS, which automatically processes computer models adding derivative-taking capabilities to the normal calculated results. The theory and applicability of the GRESS codes are described and tested against a major geohydrological modeling problem. The SWENT nuclear waste repository modeling code is used as the basis for these studies. Results for a test problem involving groundwater flow in the vicinity of the Richton Salt Dome are discussed in detail. Sensitivity results are compared with analytical, perturbation, and alternate sensitivity approaches to the problem. Five-place accuracy in these sensitivity results is verified for all cases in which the effects of nonlinearities are made sufficiently small. Conclusions are drawn as to the applicability of GRESS in the problem studied and for more general large-scale modeling sensitivity studies.
- Research Organization:
- Oak Ridge National Lab., Engineering Physics and Mathematics Div. Oak Ridge, TN 37831
- OSTI ID:
- 7198375
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 94:1; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Automated sensitivity analysis using the GRESS language
An automated sensitivity analysis procedure for the performance assessment of nuclear waste isolation systems
Automated procedure for sensitivity analysis using computer calculus
Technical Report
·
Mon Mar 31 23:00:00 EST 1986
·
OSTI ID:6022495
An automated sensitivity analysis procedure for the performance assessment of nuclear waste isolation systems
Journal Article
·
Tue Dec 31 23:00:00 EST 1985
· Nucl. Chem. Waste Manage.; (United States)
·
OSTI ID:6984655
Automated procedure for sensitivity analysis using computer calculus
Technical Report
·
Sun May 01 00:00:00 EDT 1983
·
OSTI ID:6256116
Related Subjects
052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ANALYTICAL SOLUTION
COMPUTER CODES
COMPUTERIZED SIMULATION
FLOW MODELS
FORTRAN
G CODES
GEOLOGIC DEPOSITS
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
HYDROGEN COMPOUNDS
HYDROLOGY
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
NONLINEAR PROBLEMS
NUCLEAR FACILITIES
OXYGEN COMPOUNDS
PERTURBATION THEORY
PROGRAMMING LANGUAGES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
S CODES
SALT DEPOSITS
SENSITIVITY ANALYSIS
SIMULATION
UNDERGROUND DISPOSAL
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ANALYTICAL SOLUTION
COMPUTER CODES
COMPUTERIZED SIMULATION
FLOW MODELS
FORTRAN
G CODES
GEOLOGIC DEPOSITS
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
HYDROGEN COMPOUNDS
HYDROLOGY
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
NONLINEAR PROBLEMS
NUCLEAR FACILITIES
OXYGEN COMPOUNDS
PERTURBATION THEORY
PROGRAMMING LANGUAGES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
S CODES
SALT DEPOSITS
SENSITIVITY ANALYSIS
SIMULATION
UNDERGROUND DISPOSAL
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER