Actions for Comparison of calculations and in situ results for a large, heated test room at the Waste Isolation Pilot Plant (WIPP) [electronic resource].
Comparison of calculations and in situ results for a large, heated test room at the Waste Isolation Pilot Plant (WIPP) [electronic resource].
- Published
- Washington, D.C : United States. Dept. of Energy. Office of the Assistant Secretary for Defense Programs, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (8 pages) : digital, PDF file
- Additional Creators
- Sandia National Laboratories, United States. Department of Energy. Office of the Assistant Secretary for Defense Programs, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The mission of the Waste Isolation Pilot Plant (WIPP) Project is to develop the technology for safe disposal of the radioactive Transuranic (TRU) waste forms generated by the US defense programs. The WIPP facility has been constructed in the bedded salt deposits of Southeastern New Mexico. In the existing regulatory context, the requirement is to assure that the potential repository isolates the radioactive waste from the accessible environment and mankind. This requirement means, in part, that the creep closure and waste encapsulation of the salt must be predicted far into the future, a capability which requires a significant development of predictive technology. A series of large scale in situ experiments were fielded at the WIPP specifically to provide a data base for validation of the independently developed prediction technology. In this paper, we present the results of one large scale, heated test as analyzed according to the most advanced predictive capability. The closure measurements from a large scale, heated, in situ experimental room in salt are compared to numerical calculations using the most recent predictive technology, with very good agreement, limited potentially only by the unmodeled roof fracture and separation. 9 refs., 6 figs., 1 tab.
- Report Numbers
- E 1.99:sand-89-2268
E 1.99: conf-900646--1
conf-900646--1
sand-89-2268 - Subject(s)
- Other Subject(s)
- Alpha-Bearing Wastes
- Radioactive Waste Disposal
- Underground Facilities
- Mechanical Tests
- Thermal Testing
- Calculation Methods
- Mathematical Models
- Radioactive Waste Facilities
- Regulations
- Salt Deposits
- Temperature Effects
- Thermal Conductivity
- Waste Forms
- Wipp
- Functional Models
- Geologic Deposits
- Management
- Materials
- Materials Testing
- National Organizations
- Nondestructive Testing
- Nuclear Facilities
- Physical Properties
- Pilot Plants
- Radioactive Materials
- Radioactive Wastes
- Testing
- Thermodynamic Properties
- Us Doe
- Us Organizations
- Waste Disposal
- Waste Management
- Wastes
- Note
- Published through SciTech Connect.
08/01/1990.
"sand-89-2268"
" conf-900646--1"
"DE91000080"
31. US symposium on rock mechanics, Golden, CO (USA), 18-20 Jun 1990.
Munson, D.E.; DeVries, K.L.; Callahan, G.D. - Funding Information
- AC04-76DP00789
View MARC record | catkey: 14418485