Methods and apparatus are provided for optimizing operations for a fracturing injection waste disposal well especially where the formation is damaged or tight such that pressure fall-off tests are impractical due to extended leak-off rate times. Formation closure pressure and formation stress are calculated using Instantaneous Shut-in Pressure rather than traditional methods requiring actual fracture closure.

A container holds radioactive material. A sub-criticality controller protects the radioactive material from reaching a criticality from contact with the water. The sub-criticality controller includes a metallic composition having at least one metal component and at least one borate component bonded to the at least one metal component. The metallic composition forms borates from the borate component when the metallic composition contacts the water.

A container holds radioactive material. A sub-criticality controller protects the radioactive material from reaching a criticality from contact with the water. The sub-criticality controller includes a metallic composition having at least one metal component and at least one borate component bonded to the at least one metal component. The metallic composition forms borates from the borate component when the metallic composition contacts the water.

A device comprises a raw material conveyor, a raw material mixer, a liquid waste conveying pipeline, an additive tank, a powder waste conveyor, an output pump, a liquid supply pump, a liquid supply manifold, an output manifold, a mixed liquid conveying pipeline, a high-pressure injection pump, a high-pressure pipeline, and a wellhead sealing device. The method includes: drilling a well; forming a fracture in the granite stratum; preparing a raw material; and injecting, by using a disposal device, a sand-carrying feed liquid from a high-pressure injection pump into the fracture of the underground granite stratum, so as to perform solidification. The method has low cost, high disposal efficiency, simple device structure, high usability, safety and reliability, and an effective reduction in nuclear waste contamination and hazards to the environment.

A device comprises a raw material conveyor, a raw material mixer, a liquid waste conveying pipeline, an additive tank, a powder waste conveyor, an output pump, a liquid supply pump, a liquid supply manifold, an output manifold, a mixed liquid conveying pipeline, a high-pressure injection pump, a high-pressure pipeline, and a wellhead sealing device. The method includes: drilling a well; forming a fracture in the granite stratum; preparing a raw material; and injecting, by using a disposal device, a sand-carrying feed liquid from a high-pressure injection pump into the fracture of the underground granite stratum, so as to perform solidification. The method has low cost, high disposal efficiency, simple device structure, high usability, safety and reliability, and an effective reduction in nuclear waste contamination and hazards to the environment.

A method for evaluating, selecting, and implementing at existing nuclear surface (or near surface) sites a deeply located high-level nuclear waste (HLW) disposal repository that is located directly vertically below the areal confines of that existing site, within a particular deeply located geologic rock formation. Many of these existing sites are ideal because: they are already legally permitted and/or licensed for using nuclear/radioactive materials, they already have nuclear/radioactive materials onsite that need a long-term safe disposal solution, and many of these existing sites already have onsite useful infrastructure (e.g., roads, buildings, cooling pools, equipment, machinery, personnel, and/or the like). Such existing sites include nuclear power plants (operating or decommissioned), interim spent nuclear fuel rod assemblies (SNF) surface storage sites, and/or near surface SNF storage sites. The deep HLW disposal repository may include a vertical wellbore, a lateral wellbore, and/or a human-made cavern.

A method for evaluating, selecting, and implementing at existing nuclear surface (or near surface) sites a deeply located high-level nuclear waste (HLW) disposal repository that is located directly vertically below the areal confines of that existing site, within a particular deeply located geologic rock formation. Many of these existing sites are ideal because: they are already legally permitted and/or licensed for using nuclear/radioactive materials, they already have nuclear/radioactive materials onsite that need a long-term safe disposal solution, and many of these existing sites already have onsite useful infrastructure (e.g., roads, buildings, cooling pools, equipment, machinery, personnel, and/or the like). Such existing sites include nuclear power plants (operating or decommissioned), interim spent nuclear fuel rod assemblies (SNF) surface storage sites, and/or near surface SNF storage sites. The deep HLW disposal repository may include a vertical wellbore, a lateral wellbore, and/or a human-made cavern.

A system and method to safely isolate mobile radioactive material during an emergency includes a borehole located in close proximity and at a depth sufficient to safely isolate the material and a man-made vertical-oriented gravity fracture located at the bottom end of the borehole. During an emergency, the mobile radioactive material enters the borehole and then passes from there into the gravity fracture. The mobile radioactive material may have sufficient density to further propagate the fracture vertically downward or a dense slurry or fluid could be mixed with the mobile radioactive material.

A system and method to safely isolate mobile radioactive material during an emergency includes a borehole located in close proximity and at a depth sufficient to safely isolate the material and a man-made vertical-oriented gravity fracture located at the bottom end of the borehole. During an emergency, the mobile radioactive material enters the borehole and then passes from there into the gravity fracture. The mobile radioactive material may have sufficient density to further propagate the fracture vertically downward or a dense slurry or fluid could be mixed with the mobile radioactive material.

Methods and apparatus are provided for optimizing operations for a fracturing injection waste disposal well especially where the formation is damaged or tight such that pressure fall-off tests are impractical due to extended leak-off rate times. Formation closure pressure and formation stress are calculated using Instantaneous Shut-in Pressure rather than traditional methods requiring actual fracture closure.