Long-term structural and radiological performance assessment for an enhanced abovegrade earth-mounded concrete vault
- Rogers and Associates Engineering Corp., Salt Lake City, UT (USA)
This report presents an analysis of the long-term structural and radiological performance of a hypothetical abovegrade earth-mounded concrete vault used for the disposal of low-level radioactive waste. The vault structure design is based on the application of accepted standard engineering codes. The degradation of the concrete vault and the grouted waste forms over time and the resultant changes in the leaching and migration of radionuclides through the environment are modeled using a combination of the HELP, BARRIER, PATHRAE, and PRESTO-CPG computer codes. The resultant radiological doses to a farmer living adjacent to the facility and to several types of inadvertent intruders are calculated. These calculations show the performance of this total-system treatment and disposal concept to greatly exceed the Department of Energy's performance objectives for the protection of the general public and inadvertent intruders. 12 refs., 9 figs., 3 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA); Rogers and Associates Engineering Corp., Salt Lake City, UT (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 7271871
- Report Number(s):
- DOE/LLW-78T; MISC--90003; ON: DE90006965
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
99 GENERAL AND MISCELLANEOUS
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B CODES
BIOCHEMISTRY
BUILDING MATERIALS
CHEMISTRY
COMPILED DATA
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
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DESIGN
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DOCUMENT TYPES
DOSE EQUIVALENTS
DOSIMETRY
ENVIRONMENTAL EXPOSURE PATHWAY
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LEACHING
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P CODES
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PROGRESS REPORT
RADIATION PROTECTION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
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RADIONUCLIDE KINETICS
RADIONUCLIDE MIGRATION
SECURITY
SEPARATION PROCESSES
SIMULATION
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STRUCTURAL MODELS
SYSTEM FAILURE ANALYSIS
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99 GENERAL AND MISCELLANEOUS
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B CODES
BIOCHEMISTRY
BUILDING MATERIALS
CHEMISTRY
COMPILED DATA
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
DATA
DESIGN
DISSOLUTION
DOCUMENT TYPES
DOSE EQUIVALENTS
DOSIMETRY
ENVIRONMENTAL EXPOSURE PATHWAY
ENVIRONMENTAL TRANSPORT
FAILURE MODE ANALYSIS
H CODES
HUMAN FACTORS
INFORMATION
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MASS TRANSFER
MATERIALS
NUMERICAL DATA
P CODES
PERFORMANCE TESTING
PROGRESS REPORT
RADIATION PROTECTION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
RADIONUCLIDE KINETICS
RADIONUCLIDE MIGRATION
SECURITY
SEPARATION PROCESSES
SIMULATION
SOLUBILITY
STRUCTURAL MODELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES