Patent classifications
G21F9/008
System for nuclear waste storage and monitoring
A system for storing and monitoring nuclear waste. The system includes a storage borehole having an end segment configured to store nuclear waste in a subterranean storage site location having a shale rock layer. The layer has a measured fluid overpressure in a range corresponding to greater than hydrostatic pressure to less than a lithostatic pressure from overlying rock layers. The system also includes a monitoring borehole configured to reside in the layer with an end segment of the monitoring borehole in a vicinity of the end segment of the storage borehole. The measured fluid pressure at the end of the monitoring borehole is in the fluid overpressure range.
Ion specific media removal from vessel for vitrification
Disclosed herein are systems, methods, processes, and apparatuses for treating radioactive waste, through systems designed to bind and dry radioactive media and to mechanical devices and techniques that are utilized for removal of granular media from confined spaces (vessels and tanks). In some of its various embodiments, the system processes spent ion exchange media for long-term storage.
Systems and methods for assaying a radioactive gas, and related scintillation cells
A radioactive gas assay system comprises a scintillation cell production assembly, a detector assembly, a computer assembly, and a scintillation cell destruction assembly. The scintillation cell production assembly is configured to produce a scintillation cell comprising a glass scintillator shell containing a volume of radioactive gas. The detector assembly is configured to receive the scintillation cell and to detect photons emitted thereby. The computer assembly is configured to receive data from the detector assembly to automatically calculate an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly. The scintillation cell destruction assembly is configured to receive the scintillation cell and to rupture the substantially non-porous glass scintillator shell to release the volume of radioactive gas. A method of assaying a radioactive gas, and a scintillation cell are also described.
SYSTEM FOR NUCLEAR WASTE STORAGE AND MONITORING
A system for storing and monitoring nuclear waste. The system includes a storage borehole having an end segment configured to store nuclear waste in a subterranean storage site location having a shale rock layer. The layer has a measured fluid overpressure in a range corresponding to greater than hydrostatic pressure to less than a lithostatic pressure from overlying rock layers. The system also includes a monitoring borehole configured to reside in the layer with an end segment of the monitoring borehole in a vicinity of the end segment of the storage borehole. The measured fluid pressure at the end of the monitoring borehole is in the fluid overpressure range.
SYSTEMS AND METHODS FOR ASSAYING A RADIOACTIVE GAS, AND RELATED SCINTILLATION CELLS
A radioactive gas assay system comprises a scintillation cell production assembly, a detector assembly, a computer assembly, and a scintillation cell destruction assembly. The scintillation cell production assembly is configured to produce a scintillation cell comprising a glass scintillator shell containing a volume of radioactive gas. The detector assembly is configured to receive the scintillation cell and to detect photons emitted thereby. The computer assembly is configured to receive data from the detector assembly to automatically calculate an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly. The scintillation cell destruction assembly is configured to receive the scintillation cell and to rupture the substantially non-porous glass scintillator shell to release the volume of radioactive gas. A method of assaying a radioactive gas, and a scintillation cell are also described.
Method for nuclear waste storage and monitoring
A method comprising storing nuclear waste, including identifying a subterranean storage site location having a shale rock layer. The layer has an expected fluid overpressure in a range corresponding to greater than hydrostatic pressure to less than lithostatic pressure from overlying rock layers. Storing the waste can include forming a storage borehole, with an end segment of the storage borehole located within the layer and measuring the fluid pressure in the end segment of the storage borehole. If the measured fluid pressure in the end segment of the storage borehole is in the expected fluid overpressure range, forming a monitoring borehole in the layer with an end segment of each of the monitoring boreholes being in a vicinity of the end segment of the storage borehole and storing nuclear waste in the end segment of the storage borehole. A system for storing and monitoring nuclear waste is also described.
METHOD FOR NUCLEAR WASTE STORAGE AND MONITORING
A method comprising storing nuclear waste, including identifying a subterranean storage site location having a shale rock layer. The layer has an expected fluid overpressure in a range corresponding to greater than hydrostatic pressure to less than lithostatic pressure from overlying rock layers. Storing the waste can include forming a storage borehole, with an end segment of the storage borehole located within the layer and measuring the fluid pressure in the end segment of the storage borehole. If the measured fluid pressure in the end segment of the storage borehole is in the expected fluid overpressure range, forming a monitoring borehole in the layer with an end segment of each of the monitoring boreholes being in a vicinity of the end segment of the storage borehole and storing nuclear waste in the end segment of the storage borehole. A system for storing and monitoring nuclear waste is also described.
Filling container and method for storing hazardous waste material
The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.
INTEGRATED ION-EXCHANGE DISPOSAL AND TREATMENT SYSTEM
There is disclosed a canister for interim storage and subsequent consolidation of waste materials via hot pressing. In an embodiment, the canister comprises at least one ion exchange material, and is configured to: house the ion exchange material after it is exchanged with a contaminating ion without releasing the contaminating ion; and consolidate via hot-isostatic pressing. There is also disclosed a contacting a fluid waste with an ion exchange material, wherein the ion exchange material is located in a canister; evacuating the canister; and hot isostatically pressing (HIP) the canister until it collapses under HIP conditions.
Apparatus for cleaning contaminated water from radioactive materials
Apparatus and methods for treating radioactive material, in particular for cleaning radioactive contaminated water, are described. One apparatus comprises a process chamber with a combustion zone for generating an oxygen rich gas and an oxidation zone, which is arranged to receive the oxygen rich gas from the combustion zone. The process chamber further comprises a feed opening for feeding the radioactive material into the oxidation zone and is configured to use the oxygen rich gas for oxidizing the radioactive material to obtain oxidized material. The apparatus further comprises a separation device operationally connected to an outlet of the process chamber and configured to at least partly separate the oxidized material into a gaseous fluid and a non-gaseous residue. This way a greatly reduced volume of the radioactive material is achieved, enabling safe and efficient handling and/or compact and space-saving disposal of the radioactive material.