Verification and benchmarking of PORFLO: an equivalent porous continuum code for repository scale analysis
The objective of this work was to perform an assessment of prediction capabilities and features of the PORFLO code in relation to its intended use in the Basalt Waste Isolation Project. This objective was to be accomplished through a code verification and benchmarking task. Results were to be documented which either support correctness of prediction capabilities or identify areas of intended application in which the code exhibits weaknesses. A test problem set consisting of 10 problems was developed. Results of PORFLO simulations of these problems were provided for use in this work. The 10 problems were designed to test the three basic computational capabilities or categories of the code. Broken down by physical process, these are heat transfer, fluid flow, and radionuclide transport. Two verification problems were included within each of these categories. They were problems designed to test basic features of PORFLO for which analytical solutions are available for use as a known comparison basis. Hence they are referred to as verification problems. Of the remaining four problems, one repository scale problem representative of intended PORFLO use within BWIP was included in each of the three basic capabilities categories. The remaining problem was a case specifically designed to test features of decay and retardation in radionuclide transport. These four problems are referred to as benchmarking problems, because results computed with an additional computer code were used as a basis for comparison. 38 figures.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6361272
- Report Number(s):
- PNL-5044; ON: DE85004116
- Resource Relation:
- Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
54 ENVIRONMENTAL SCIENCES
COMPUTER CODES
P CODES
BENCHMARKS
VALIDATION
BASALT
FLUID FLOW
GROUND WATER
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
POROUS MATERIALS
RADIONUCLIDE MIGRATION
TWO-DIMENSIONAL CALCULATIONS
ENERGY TRANSFER
ENVIRONMENTAL TRANSPORT
HYDROGEN COMPOUNDS
IGNEOUS ROCKS
MASS TRANSFER
MATERIALS
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
ROCKS
TESTING
VOLCANIC ROCKS
WASTES
WATER
052002* - Nuclear Fuels- Waste Disposal & Storage
053000 - Nuclear Fuels- Environmental Aspects
990200 - Mathematics & Computers
520301 - Environment
Aquatic- Radioactive Materials Monitoring & Transport- Water- (1987)