共 50 条
- [34] Design and Structural Safety Evaluation of Transfer Cask for Dry Storage System of PWR Spent Nuclear Fuel [J]. JOURNAL OF NUCLEAR FUEL CYCLE AND WASTE TECHNOLOGY, 2023, 21 (04): : 503 - 516
- [35] Conceptual Design, Development, and Preliminary Safety Evaluation of a PWR Dry Storage Module for Spent Nuclear Fuel [J]. APPLIED SCIENCES-BASEL, 2022, 12 (09):
- [36] A Preliminary Evaluation on CO2 Storage Capacity of the Southwestern Part of Ulleung Basin, Offshore, East Sea [J]. ECONOMIC AND ENVIRONMENTAL GEOLOGY, 2012, 45 (01): : 41 - 48
- [37] Design and Structural Safety Evaluation of the High Burn-up PWR Spent Nuclear Fuel for Storage Cask [J]. JOURNAL OF NUCLEAR FUEL CYCLE AND WASTE TECHNOLOGY, 2024, 22 (02): : 201 - 210
- [38] Evaluation of the CO2 Storage Capacity by the Measurement of the scCO(2) Displacement Efficiency for the Sandstone and the Conglomerate in Janggi Basin [J]. ECONOMIC AND ENVIRONMENTAL GEOLOGY, 2016, 49 (06): : 469 - 477
- [39] CO2 Geological Storage in the Province of Quebec, Canada - Capacity Evaluation of the St. Lawrence Lowlands basin [J]. GHGT-11, 2013, 37 : 5093 - 5100