Postclosure performance assessment of the SCP (Site Characterization Plan) conceptual design for horizontal emplacement [electronic resource] : Revision 1.
- Published:
- Columbus, Ohio : Battelle Memorial Institute, 1987.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Additional Creators:
- Battelle Memorial Institute and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- This report is a preliminary postclosure performance assessment of the repository design specified in the Site Characterization Plan Conceptual Design Report (SCP-CDR) for horizontal emplacement of high-level nuclear waste. At the time that these analyses were done, horizontal emplacement was the preferred orientation for the waste packages but vertical emplacement is now the reference design. This assessment consists of (1) a review of the regulatory requirements and strategy to demonstrate compliance with these requirements, (2) an analysis of the performance of the total repository system, (3) an analysis of the thermomechanical behavior of the repository, (4) an analysis of brine mobility in the repository, (5) an analysis of the waste package performance, (6) an analysis of the performance of seals, and (7) comments on the sensitivity of the various performance measures to uncertainties in the data and models. These are preliminary analyses and, in most cases, involve bounding calculations of the repository behavior. They have several purposes including (1) assessing how well this conceptual design ''measures up'' against requirements, (2) gaining experience in implementing the performance assessment strategy and tools and thereby learning where improvements are needed, (3) helping to identify needed data, and (4) helping to indicate required design modifications. 26 refs., 40 figs., 20 tabs.
- Report Numbers:
- E 1.99:bmi/onwi/c-300
bmi/onwi/c-300 - Subject(s):
- Other Subject(s):
- Design
- Evaluation
- High-Level Radioactive Wastes
- Underground Disposal
- Radioactive Waste Facilities
- Site Characterization
- Compliance
- Radioactive Waste Management
- Regulations
- Salt Deposits
- Spent Fuels
- Energy Sources
- Fuels
- Geologic Deposits
- Management
- Materials
- Nuclear Facilities
- Nuclear Fuels
- Radioactive Materials
- Radioactive Wastes
- Reactor Materials
- Waste Disposal
- Waste Management
- Wastes
- Note:
- Published through SciTech Connect.
08/01/1987.
"bmi/onwi/c-300"
"TI89000048"
Not Available. - Funding Information:
- AC02-87CH10290
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