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Requirement for radiological assessments of disposal of radioactive waste in seabed sediments
317A
General underground storage 905504 Centrifuge modelling of heat-generating waste disposal Poorooshasb, F; James, R G Can Geotech J V26, N4, Nov 1989, P640-652 Model simulation of the free fall option for sub-seabed disposal of radioactive waste using the Cambridge University geotechnical centrifuge is described. Soil (speswhite kaolin) deformation, hole closure behind the projectile, depth of penetration, pore pressure changes due to penetration, and consequences of heat emission from the penetrator were examined. Results are compared to those of large scale field tests and analytical studies. 905505 Sweden's research and development program for thermal energy storage Sellberg, B Tannig Underground Space Techaol I/5, N1/2, 1990, P85-89 The basic design and principles of subsurface heat storage are outlined: systems using pipes in soils, boreholes in rocks, excavated pits, rock caverns, or aquifers. Research activities in Sweden over the past 6 years are described. Potential for the future and required technology and cost efficiency improvements are discussed. 905506 Modelling the mechanical behaviour of a spherical cavity in saltrock: comparison between elasto-viscoplastic and rigidviseoplastic models for underground storage of gas in saitrock (In French) Durup, J G Proc International Symposium on Rock at Great Depth, Pau, 28-31 August 1989 I1"2, P595-603. Publ Rotterdam: A A Balkema. 1989 When a solution mined cavity in salt is used for gas storage, variations in cavity pressure lead to changes in cavity volume and the surrounding stress field. These may be studied using different numerical models. Salt behaviour is described by a combination of a linear elastic law and Lemaitre's viscoplastic law. Finite element modelling using the code Cysiphe gives a semi-analytical elastoviscoplastic analysis for simple geometries. An analytical solution can be obtained if elastic deformation before onset of viscoplasticity is ignored (the rigidviscoplastic solution). Despite relative simplicity, these easy to use solutions give satisfactory results.
Radioactive waste disposal
905508 Excavation response in respect of the repository concept for the Konrad mine as seen by the mining authority Roehl,_W Proc NEA Workshop on Excavation Response in Geological Repositories for Radioactive Waste, Winnipeg, 26-28 April 1988 P515-528. Publ France: OECD, 1989 The Konrad iron ore mine is being considered for use as a radioactive waste repository. To study excavation response, there will be 3 areas of study, rock mechanics data, efficiency of seals at the entrance to deposit chambers, and convergence and mining subsidence. For rock mechanics data, stability of excavation will be studied by calculation and in situ testing of a drift panel, stability analysis of ~ shaft and study of the response of overlying strata to variations in rock permeability. Design of the seals is outlined and an in situ test proposed. During experimental driving of the repository, convergence, subsidence and surrounding rock response will be monitored. 905509 Requirement for radioiogical assessments of disposal of radioactive waste in seabed sediments Mobbs, S F Proc Conference on Disposal of Radioactive Waste in Seabed Sediments, Oxford, 20-21 September 1988 P17-28. Publ London: Graham and Trotman, 1989 (Advances in Underwater Technology, Ocean Science and Offshore Engineering, VI8) Post disposal radiological impact is assessed for the cases of waste emplaced by freefall penetrator into unconsolidated sediment and by disposal in a borehole through unconsolidated and iithified sediments to the bedrock interface. Risks due to emplacement difficulties, geological complications, and human intrusion are examined. Sensitivity analysis is also included. Important material parameters in these analyses are little known and research in this area is essential. 9O5510 Radiological assessment of the consequences of disposal of high-level radioactive waste in subseabed sediments Stanners, D A: Flebus, C; de Marsily, G; Poulin, M; Behrendt, V; Karpf, A; Ensminger, D A; Hutchinson, B L; Kane, P; Klett, R D; Mobbs, S F Proc Conference on Disposal of Radioactive Waste in Seabed Sediments, Oxford, 20-21 September 1988 P29-48. Publ London: Graham and Trotman, 1989 (Advances in Underwater Technology, Ocean Science and Offshore Engineering, V18) Assessments were made using deterministic and stochastic methods for the following cases: waste buried as specified and all barriers perform as anticipated; one or more components of the system behaves abnormally; and for the case of transportation accidents.
9O5507 In-situ testing at the U.S. Department of Energy's Waste Isolation Pilot Plant Matalucci, R V Tunnlg Underground Space Technol V5, N1/2, 1990, P119133
905511 Shaft sealing for nuclear waste repositories Sitz, P; Koeckritz, V; Oellers, T Proc Conference on Shaft Engineering, Harrogate, 5-7 June 1989 P345-352. Publ London: IMM, 1989
The WIPP is in rock salt at depth 659m. Thermal/structural interaction (heater) tests, plugging and sealing tests, and waste package performance tests have been carried out to examine the ability of the plant to adequately confine hot waste and isolate radiation from the environment. In some cases results can be compared to those of laboratory simulations. Long term room and pillar stability, stress levels, permeability, and seal performance are discussed. Quality assurance and documentation procedures are described.
In the multibarrier concept of radioactive waste disposal, shaft linings are important to avert migration of nuclides. New lining systems consider a distinction between the static abutment and the sealing element. Calculations for the static abutment are made using 2D and 3D finite element programs. The application of clay and clay-sand mixture as well as asphalt and bitumen sealings is considered. Seals for radioactive waste must also consider the extra loading case, such as thermal stress caused by cement hydration heat, and stress caused by
© 1990 Pergamon Press pic. Reproduction not permitted
General underground storage 905504 Centrifuge modelling of heat-generating waste disposal Poorooshasb, F; James, R G Can Geotech J V26, N4, Nov 1989, P640-652 Model simulation of the free fall option for sub-seabed disposal of radioactive waste using the Cambridge University geotechnical centrifuge is described. Soil (speswhite kaolin) deformation, hole closure behind the projectile, depth of penetration, pore pressure changes due to penetration, and consequences of heat emission from the penetrator were examined. Results are compared to those of large scale field tests and analytical studies. 905505 Sweden's research and development program for thermal energy storage Sellberg, B Tannig Underground Space Techaol I/5, N1/2, 1990, P85-89 The basic design and principles of subsurface heat storage are outlined: systems using pipes in soils, boreholes in rocks, excavated pits, rock caverns, or aquifers. Research activities in Sweden over the past 6 years are described. Potential for the future and required technology and cost efficiency improvements are discussed. 905506 Modelling the mechanical behaviour of a spherical cavity in saltrock: comparison between elasto-viscoplastic and rigidviseoplastic models for underground storage of gas in saitrock (In French) Durup, J G Proc International Symposium on Rock at Great Depth, Pau, 28-31 August 1989 I1"2, P595-603. Publ Rotterdam: A A Balkema. 1989 When a solution mined cavity in salt is used for gas storage, variations in cavity pressure lead to changes in cavity volume and the surrounding stress field. These may be studied using different numerical models. Salt behaviour is described by a combination of a linear elastic law and Lemaitre's viscoplastic law. Finite element modelling using the code Cysiphe gives a semi-analytical elastoviscoplastic analysis for simple geometries. An analytical solution can be obtained if elastic deformation before onset of viscoplasticity is ignored (the rigidviscoplastic solution). Despite relative simplicity, these easy to use solutions give satisfactory results.
Radioactive waste disposal
905508 Excavation response in respect of the repository concept for the Konrad mine as seen by the mining authority Roehl,_W Proc NEA Workshop on Excavation Response in Geological Repositories for Radioactive Waste, Winnipeg, 26-28 April 1988 P515-528. Publ France: OECD, 1989 The Konrad iron ore mine is being considered for use as a radioactive waste repository. To study excavation response, there will be 3 areas of study, rock mechanics data, efficiency of seals at the entrance to deposit chambers, and convergence and mining subsidence. For rock mechanics data, stability of excavation will be studied by calculation and in situ testing of a drift panel, stability analysis of ~ shaft and study of the response of overlying strata to variations in rock permeability. Design of the seals is outlined and an in situ test proposed. During experimental driving of the repository, convergence, subsidence and surrounding rock response will be monitored. 905509 Requirement for radioiogical assessments of disposal of radioactive waste in seabed sediments Mobbs, S F Proc Conference on Disposal of Radioactive Waste in Seabed Sediments, Oxford, 20-21 September 1988 P17-28. Publ London: Graham and Trotman, 1989 (Advances in Underwater Technology, Ocean Science and Offshore Engineering, VI8) Post disposal radiological impact is assessed for the cases of waste emplaced by freefall penetrator into unconsolidated sediment and by disposal in a borehole through unconsolidated and iithified sediments to the bedrock interface. Risks due to emplacement difficulties, geological complications, and human intrusion are examined. Sensitivity analysis is also included. Important material parameters in these analyses are little known and research in this area is essential. 9O5510 Radiological assessment of the consequences of disposal of high-level radioactive waste in subseabed sediments Stanners, D A: Flebus, C; de Marsily, G; Poulin, M; Behrendt, V; Karpf, A; Ensminger, D A; Hutchinson, B L; Kane, P; Klett, R D; Mobbs, S F Proc Conference on Disposal of Radioactive Waste in Seabed Sediments, Oxford, 20-21 September 1988 P29-48. Publ London: Graham and Trotman, 1989 (Advances in Underwater Technology, Ocean Science and Offshore Engineering, V18) Assessments were made using deterministic and stochastic methods for the following cases: waste buried as specified and all barriers perform as anticipated; one or more components of the system behaves abnormally; and for the case of transportation accidents.
9O5507 In-situ testing at the U.S. Department of Energy's Waste Isolation Pilot Plant Matalucci, R V Tunnlg Underground Space Technol V5, N1/2, 1990, P119133
905511 Shaft sealing for nuclear waste repositories Sitz, P; Koeckritz, V; Oellers, T Proc Conference on Shaft Engineering, Harrogate, 5-7 June 1989 P345-352. Publ London: IMM, 1989
The WIPP is in rock salt at depth 659m. Thermal/structural interaction (heater) tests, plugging and sealing tests, and waste package performance tests have been carried out to examine the ability of the plant to adequately confine hot waste and isolate radiation from the environment. In some cases results can be compared to those of laboratory simulations. Long term room and pillar stability, stress levels, permeability, and seal performance are discussed. Quality assurance and documentation procedures are described.
In the multibarrier concept of radioactive waste disposal, shaft linings are important to avert migration of nuclides. New lining systems consider a distinction between the static abutment and the sealing element. Calculations for the static abutment are made using 2D and 3D finite element programs. The application of clay and clay-sand mixture as well as asphalt and bitumen sealings is considered. Seals for radioactive waste must also consider the extra loading case, such as thermal stress caused by cement hydration heat, and stress caused by
© 1990 Pergamon Press pic. Reproduction not permitted