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Effect of Sulfide and Chloride Ions on Pitting Corrosion of Type 316 Austenitic Stainless Steel in Groundwater Conditions Using Response Surface Methodology.
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- Materials (1996-1944), 2024, v. 17, n. 1, p. 178, doi. 10.3390/ma17010178
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- Article
Applying state‐of‐the‐art microscopy techniques to understand the degradation of copper for nuclear waste canisters.
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- Materials & Corrosion / Werkstoffe und Korrosion, 2023, v. 74, n. 11, p. 1619, doi. 10.1002/maco.202213680
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- Article
Development of a 2D model for rapid estimation of sulfide corrosion of copper canisters in a spent nuclear fuel repository.
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- Materials & Corrosion / Werkstoffe und Korrosion, 2023, v. 74, n. 11, p. 1823, doi. 10.1002/maco.202313746
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- Article
Long-term sinking of nuclear waste canisters in salt formations by low-stress creep at high temperature.
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- Acta Geotechnica, 2023, v. 18, n. 7, p. 3469, doi. 10.1007/s11440-023-01900-w
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- Article
Time Dependent Evolution of Heat and Stress Field in Granite-clay System Representing Geological Disposal Scheme for High Level Radioactive Wastes.
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- Journal of the Geological Society of India, 2023, v. 99, n. 7, p. 941, doi. 10.1007/s12594-023-2415-9
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- Article
Characterization of Compacted Ca- and Na-Bentonite with Copper Corrosion Products in the KAERI Underground Research Tunnel.
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- Minerals (2075-163X), 2023, v. 13, n. 7, p. 898, doi. 10.3390/min13070898
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- Article
Impact of microbial processes on the safety of deep geological repositories for radioactive waste.
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- Frontiers in Microbiology, 2023, v. 14, p. 1, doi. 10.3389/fmicb.2023.1134078
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- Article
Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks.
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- Defence Technology, 2023, v. 21, p. 116, doi. 10.1016/j.dt.2022.08.002
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- Article
A high compatibility SiOCN coating on stainless steel.
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- Journal of Materials Science, 2023, v. 58, n. 8, p. 3790, doi. 10.1007/s10853-023-08252-6
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- Article
Corrosion evaluation for engineered barriers in crystalline host rock – challenges for container development in the German site selection process.
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- 2023
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- Abstract
Laser-Based Characterisation of the Copper Uranyl Sulphate, Johannite.
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- Minerals (2075-163X), 2022, v. 12, n. 11, p. 1419, doi. 10.3390/min12111419
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- Article
‚We have a solution’: Delivering on the promise to take national responsibility for nuclear waste management.
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- Journal for Technology in Theory & Practice / Zeitschrift für Technikfolgenabschätzung in Theorie und Praxis (TATuP), 2022, v. 31, n. 3, p. 31, doi. 10.14512/tatup.31.3.31
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- Article
Nanoindentation Investigation of Chloride-Induced Stress Corrosion Crack Propagation in an Austenitic Stainless Steel Weld.
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- Metals (2075-4701), 2022, v. 12, n. 8, p. 1243, doi. 10.3390/met12081243
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- Article
Growth and Persistence of an Aerobic Microbial Community in Wyoming Bentonite MX-80 Despite Anoxic in situ Conditions.
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- Frontiers in Microbiology, 2022, v. 13, p. 1, doi. 10.3389/fmicb.2022.858324
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- Article
Exact Analytical Solution of the Nonstationary Problem of Calculation of Temperature and Mechanical-Stress Fields in a Two-Layer Cylinder and Its Application for the Verification of Numerical Models.
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- High Temperature, 2022, v. 60, n. 2, p. 222, doi. 10.1134/S0018151X22020298
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- Article
Three‐dimensional thermal modeling and dimensioning design in the nuclear waste repository.
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- International Journal for Numerical & Analytical Methods in Geomechanics, 2022, v. 46, n. 4, p. 779, doi. 10.1002/nag.3321
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- Article
Effect of Stress Magnitude on Pit Growth Rate of 304 Austenitic Stainless Steel in Chloride Environments.
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- Metals (2075-4701), 2021, v. 11, n. 9, p. 1415, doi. 10.3390/met11091415
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- Article
Response of compacted bentonite to hyperalkalinity and thermal history.
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- Scientific Reports, 2021, v. 11, n. 1, p. 1, doi. 10.1038/s41598-021-95023-5
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- Article
Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters.
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- NPJ Materials Degradation, 2021, v. 5, n. 1, p. 1, doi. 10.1038/s41529-021-00174-5
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- Article
Reimagining Nuclear Engineering: To heal the divide over nuclear energy, the field needs to move from advocacy to understanding.
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- Issues in Science & Technology, 2021, v. 37, n. 3, p. 64
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- Article
Deep Time: The End of an Engagement For all its flaws, US nuclear waste policy at least relied on a sense of a moral responsibility toward the present and future. That may now be changing.
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- Issues in Science & Technology, 2021, v. 37, n. 3, p. 70
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- Article
Ultrasonic and acoustic techniques.
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- Insight: Non-Destructive Testing & Condition Monitoring, 2021, v. 63, n. 2, p. 123
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- Article
Dominant substructural vibration modes for fully-loaded spent nuclear fuel canisters.
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- Computational Mechanics, 2021, v. 67, n. 1, p. 365, doi. 10.1007/s00466-020-01937-8
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Evaluation of the corrosion behavior of modern spent nuclear fuels under repository conditions.
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- Safety of Nuclear Waste Disposal, 2021, v. 1, p. 91, doi. 10.5194/sand-1-91-2021
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- Article
Anaerobic corrosion of carbon steel in compacted bentonite exposed to natural Opalinus clay porewater: Bentonite alteration study.
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- Safety of Nuclear Waste Disposal, 2021, v. 1, p. 103, doi. 10.5194/sand-1-103-2021
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- Article
The European DISCO project: deep geological disposal of modern spent nuclear fuel.
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- Safety of Nuclear Waste Disposal, 2021, v. 1, p. 233, doi. 10.5194/sand-1-233-2021
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- Article
Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part I.
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- NPJ Materials Degradation, 2020, v. 4, n. 1, p. 1, doi. 10.1038/s41529-020-0117-y
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- Article
PolyCSAM: BOOSTING COLD SPRAY ADDITIVE MANUFACTURING INTO FULL-SCALE PRODUCTION: A joint Canadian venture launches a new facility with an innovative hybrid approach to cold spray additive manufacturing.
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- Advanced Materials & Processes, 2020, v. 178, n. 3, p. 39, doi. 10.31399/asm.amp.2020-03.p039
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- Article
Quantifying the Effectiveness of Patterning, Test Conditions, and DIC Parameters for Characterization of Plastic Strain Localization.
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- Experimental Mechanics, 2020, v. 60, n. 1, p. 3, doi. 10.1007/s11340-019-00510-6
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- Article
Evaluation of Evaporative Emission and Feasibility of an Onboard Refueling Vapor Recovery System for Scooters.
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- Energies (19961073), 2019, v. 12, n. 4, p. 704, doi. 10.3390/en12040704
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- Article
Preliminary Assessment of Criticality Safety Constraints for Swiss Spent Nuclear Fuel Loading in Disposal Canisters.
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- Materials (1996-1944), 2019, v. 12, n. 3, p. 494, doi. 10.3390/ma12030494
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- Article
Identification of 3D fracture distribution and fracture connectivity by combined Ground Penetrating Radar imagery and tracer tests at the Äspö Hard Rock Laboratory, Sweden.
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- Geophysical Research Abstracts, 2019, v. 21, p. 1
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- Article
The Role of Glide during Creep of Copper at Low Temperatures.
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- Metals (2075-4701), 2018, v. 8, n. 10, p. 772, doi. 10.3390/met8100772
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- Article
1D simulation of canister galvanic corrosion in saturated compacted bentonite.
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- Materials & Corrosion / Werkstoffe und Korrosion, 2018, v. 69, n. 9, p. 1163, doi. 10.1002/maco.201710014
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- Article
Passive Fuel Cell Heat Recovery Using Heat Pipes to Enhance Metal Hydride Canisters Hydrogen Discharge Rate: An Experimental Simulation.
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- Energies (19961073), 2018, v. 11, n. 4, p. 915, doi. 10.3390/en11040915
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- Article
Comparison of Tagging Technologies for Safeguards of Copper Canisters for Nuclear Spent Fuel.
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- Sensors (14248220), 2018, v. 18, n. 4, p. 929, doi. 10.3390/s18040929
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- Article
Environmental Effects of Cavitation Technology for Radioactive Waste Management.
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- Chemical & Petroleum Engineering, 2018, v. 53, n. 11/12, p. 738, doi. 10.1007/s10556-018-0414-2
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- Article
Physicochemical and Geotechnical Alterations to MX-80 Bentonite at the Waste Canister Interface in an Engineered Barrier System.
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- Geosciences (2076-3263), 2017, v. 7, n. 3, p. 69, doi. 10.3390/geosciences7030069
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- Article
Corrosion assessment of canister for the disposal of spent nuclear fuel in crystalline rock in Taiwan.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 194, doi. 10.1080/1478422X.2017.1285855
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- Article
Czech national programme and disposal canister concept.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 6, doi. 10.1080/1478422X.2017.1300379
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- Article
Nature of the near-field environment in a deep geological repository and the implications for the corrosion behaviour of the container.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 25, doi. 10.1080/1478422X.2017.1330736
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- Article
Design development of a copper-coated canister for the disposal of spent fuel in a deep geological repository in Opalinus Clay.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 31, doi. 10.1080/1478422X.2017.1292200
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- Article
Insights from post-test examination of three packages from the MiniCan test series of copper-cast iron canisters for geological disposal of spent nuclear fuel: impact of the presence and density of bentonite clay.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 54, doi. 10.1080/1478422X.2017.1296224
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- Article
The anaerobic corrosion of carbon steel in saturated compacted bentonite in the Swiss repository concept.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 113, doi. 10.1080/1478422X.2017.1316088
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- Article
Studies on corrosion behaviour of low carbon steel canister with and without γ-irradiation in China’s HLW disposal repository.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 136, doi. 10.1080/1478422X.2017.1348762
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- Article
Sulphide-transport control of the corrosion of copper canisters.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 210, doi. 10.1080/1478422X.2017.1300363
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- Article
Summary of studies on the anaerobic corrosion of carbon steel in alkaline media in support of the Belgian supercontainer concept.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, p. 217, doi. 10.1080/1478422X.2017.1356981
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- Article
Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors.
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- International Journal of Energy Research, 2016, v. 40, n. 14, p. 1901, doi. 10.1002/er.3464
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- Article
Influence of sample preparation on MX-80 bentonite microstructure.
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- Clay Minerals, 2016, v. 51, n. 2, p. 189, doi. 10.1180/claymin.2015.051.2.06
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- Article
Distinguishing between more and less suitable bentonites for storage of high-level radioactive waste.
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- Clay Minerals, 2016, v. 51, n. 2, p. 289, doi. 10.1180/claymin.2016.051.2.14
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- Article