A compendium of the data used with the SYVAC3-CC3 system model
AECL is evaluating a concept for disposing of nuclear fuel waste from Canada`s CANDU reactors deep in plutonic rock of the Canadian Shield. As part of this evaluation, AECL has developed models of the physical, chemical, geological and biological processes that could occur in a sealed disposal vault designed to limit transport of contaminants to the accessible environment over thousands of years. The mathematical models of the transport of radionuclides and toxic chemicals from nuclear fuel waste to the environment are incorporated into a computer model named the Systems Variability Analysis Code, Generation 3, and Canadian Concept Model, Generation 3 (SYVAC3-CC3). This report reproduces the data in the master database used by SYVAC3-CC3 for the postclosure assessment of deep geological disposal. These data are derived from a major program of laboratory and field studies conducted by AECL Research over the past fifteen years, including the investigations at an Underground Research Laboratory excavated to a depth of 450 meters in a large granitic batholith within the Whiteshell Research Area near Lac du Bonnet, Manitoba; conceptual engineering studies; detailed analyses of specific features, events and processes; and published literature. The data represent characteristics of a hypothetical vault, certain geological characteristics of the Whiteshell Research Area, and a general surface environment with a human population living a rural lifestyle on a portion of the Canadian Shield in central Canada. The data are stored in a master database, which is used with a suite of computer programs to create the input data files used by SYVAC3-CC3.
- Research Organization:
- Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.
- OSTI ID:
- 80365
- Report Number(s):
- AECL-11013-Corr.; COG-93-455; TRN: 95:016197
- Resource Relation:
- Other Information: PBD: Dec 1994
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-temperature uniaxial and triaxial compression tests on URL rock samples from boreholes 209-018-EXT4 and 209-030-DIL1. Report No. MRL 90-109(TR)
Development of a system model for the postclosure assessment of a concept for geological disposal of Canada`s nuclear fuel waste