Horizontal and vertical measurements of drift closures have been made with a manually operated tape extensometer since about 6 weeks after the emplacement of the spent fuel at various locations along the length of the drifts. The averaged closures are less than 0.6 mm from the onset of measurements through about two years after the spent fuel emplacement. These results have been compared with thermo-elastic finite element calculations using measured medium properties. The comparisons show that most of the closure of the drifts occurred between the time the spent fuel was emplaced and the time of first measurement. The comparisons show that the results track each other, in that where closure followed by dilation is measured, the calculations...
International audienceIn this study, we analyzed the influence of the excavation size and the sequen...
The Spent Fuel Test-Climax (SFT-C) was located 420 m below surface in the Climax Stock granite on th...
If we are to believe our predictions of the thermomechanical behavior of the material surrounding a ...
During the time period of February to April, 1979, twelve rod extensometers and twenty-two convergen...
A generic test of geological storage of spent-fuel assemblies from an operating nuclear reactor in C...
The Spent Fuel Test-Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep geo...
The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on t...
Both operational and technical objectives are being pursued at the Spent-Fuel Test-Climax (SFT-C). T...
A generic test of the geologic storage of spent-fuel assemblies from an operating nuclear reactor is...
The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on t...
A test is conducted in which spent fuel assemblies from an operating commercial nuclear power reacto...
The Spent Fuel Test - Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep g...
The in situ modulus of the Climax granite in the Spent Fuel Test (SFT-C) area of the Nevada Test Sit...
The technical feasibility of short-term storage and retrieval of spent nuclear fuel assemblies has r...
The Lawrence Livermore Laboratory (LLL), as part of the Nevada Nuclear Waste Storage Investigations ...
International audienceIn this study, we analyzed the influence of the excavation size and the sequen...
The Spent Fuel Test-Climax (SFT-C) was located 420 m below surface in the Climax Stock granite on th...
If we are to believe our predictions of the thermomechanical behavior of the material surrounding a ...
During the time period of February to April, 1979, twelve rod extensometers and twenty-two convergen...
A generic test of geological storage of spent-fuel assemblies from an operating nuclear reactor in C...
The Spent Fuel Test-Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep geo...
The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on t...
Both operational and technical objectives are being pursued at the Spent-Fuel Test-Climax (SFT-C). T...
A generic test of the geologic storage of spent-fuel assemblies from an operating nuclear reactor is...
The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on t...
A test is conducted in which spent fuel assemblies from an operating commercial nuclear power reacto...
The Spent Fuel Test - Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep g...
The in situ modulus of the Climax granite in the Spent Fuel Test (SFT-C) area of the Nevada Test Sit...
The technical feasibility of short-term storage and retrieval of spent nuclear fuel assemblies has r...
The Lawrence Livermore Laboratory (LLL), as part of the Nevada Nuclear Waste Storage Investigations ...
International audienceIn this study, we analyzed the influence of the excavation size and the sequen...
The Spent Fuel Test-Climax (SFT-C) was located 420 m below surface in the Climax Stock granite on th...
If we are to believe our predictions of the thermomechanical behavior of the material surrounding a ...