..., such as high-level waste or spent nuclear fuel. With the aim of performing generic research that will support future site-specific work [9], we consider a generic salt repository and we assume in-drift emplacement of the waste packages parallel to the drift axis. After emplacement of the waste packages...

... considered, we have assumed in-drift emplacement of the waste packages and subsequent backfill of the drifts with crushed salt. In such scenario, as the natural salt host rock creeps under the effect of temperature and deviatoric stresses, the backfill will reconsolidate progressively. It is expected...

... materials and corrosion Upstream Oil & Gas steel over-pack gallery empty space corrosion product flowline corrosion Subsurface Corrosion solid waste management steel corroded product corrosion process evolution waste package host rock disposal cell hlw disposal cell steel corrosion...

... the mechanical and hydraulic barrier integrity of the repository over the long-term. The design adopted involves metallic waste packages horizontally disposed in drifts subsequently backfilled with crushed salt. Some of the THM interactions studied concern porosity and permeability changes within the backfill...

... high-level radioactive waste repository waste package ARMA 11-243 Coupled Thermal-Hydrological-Mechanical-Chemical Analyses of a Repository in Clay/Shale for High-Level Waste Stone, C. M Martinez, M. J., Dewers, T., Hansen, F.D, Hardin, E. L., and Argüello, J. G. Sandia National Laboratories...

... by the waste packages and by hypothetical gas generation within the rooms. The physical and mechanical characteristics of some of the waste packaging are appreciably different from the assumed waste upon which the original compliance was based and approved. These analyses provide insight into the structural...

... ABSTRACT: The proposed nuclear waste repository at Yucca Mountain, Nevada currently includes a minimum of 50 years forced ventilation inside of emplacement drifts prior to repository closure. To regulate the heat generated from emplaced waste packages, the ventilation during the pre-closure...

... ABSTRACT: This paper presents a model for estimating waste package surface temperature within the potential high-level waste (HLW) repository at Yucca Mountain, Nevada, USA. In the current repository design, HLW will be disposed in waste packages that will be emplaced in unbackfilled...

... ABSTRACT: The Yucca Mountain Site Characterization Project has completed two pilot-scale tests of the potential repository drip shield configuration over waste packages. One test included backfill over the drip shield and one did not. Both tests were constructed at ¬ scale of the potential...

... ABSTRACT: Changing designs of a proposed nuclear waste repository, such as waste package inventories and invert materials, affect Thermal-Hydrologic (TH) environment around the repository drift significantly, and alter the performance of the repository. Design sensitivity of a potential...

... a coarse granular material, and (2) a standard coarse granular backfill. Neither the capillary barrier nor backfill are part of the current repository design but may be added at a later date. The current repository design uses a drip shield to protect the waste packages from rock falls and water intrusion...

... Engineering criteria application US government cask objective repository design approach Yucca Mountain Project procedure design component reference information base Design Methodology risk management strength functional requirement rock excavation waste package ABSTRACT...

... as the functional unit, is proposed. Such a unit reduces temperatures and temperature gradients in the vicinity of a waste package and in the repository near field, reducing leach rates from packages and thermomechanical disturbance of the rock mass. Preliminary analyses confirm the mode of performance...

... plane stress solid waste management Upstream Oil & Gas overpack defense high-level waste package waste package radial stress waste repository Battelle Memorial Institute spec inc salt pressure maximum radial stress Reservoir Characterization nuclear waste isolation air gap...

... at each site, with the determination of the resulting radial salt pressure on the waste package being the parameter of primary interest. INTRODUCTION Background The development of nuclear energy has created a need for the safe disposal of radioactive wastes. The National Waste Ter- minal Storage (NWTS...