摘要:
Apparatuses, processes and methods for the separation, isolation, or removal of specific radioactive isotopes from liquid radioactive waste, these processes and methods employing isotope-specific media (ISM). In some embodiments, the processes and methods further include the vitrification of the separated isotopes, generally with the ISM; this isotope-specific vitrification (ISV) is often a step in a larger scheme of preparing the radioactive isotopes for long-term storage or other disposition. A variety of ISM are disclosed.
摘要:
Systems and processes for reducing the volume of radioactive waste materials through pyrolysis and vitrification carried out by microwave heating and, in some instances, a combination of microwave heating and inductive heating. In some embodiments, the microwave-enhanced vitrification system comprises a microwave system for treating waste material combined with a modular vitrification system that uses inductive heating to vitrify waste material. The final product of the microwave-enhanced vitrification system is a denser, compacted radioactive waste product.
摘要:
Systems and methods are disclosed herein for a robotic manipulator arm deployment and control system. The arm is operable to deploy tools, and one or more sensors including a non-contact sensor and a dynamic measurement unit. The non-contact sensor may be used for measuring range and bearing to objects in the operating space in polar coordinates to generate an electronic three-dimensional map of the operating space. The purpose of a three-dimensional map of the operating space is to define the boundaries of the operating space and any infrastructure or objects in the space that may restrict the RMA's range of motion in the space.
摘要:
A mobile nuclear waste processing system comprising: a first intermodal shipping container including a main enclosure, an inlet leading into the main enclosure, and an outlet leading out of the main enclosure; a solids removal module disposed within the main enclosure, the solids removal module including a filter configured to receive a flow of fluid and remove at least some solids from the fluid; a first conduit extending through the inlet of the main enclosure and configured to direct the fluid from a fluid supply tank to the solids removal module; a second conduit extending through the outlet of the main enclosure and configured to direct the fluid from the solids removal module out of the main enclosure; and a control system configured to monitor flow of the fluid through solids removal module.
摘要:
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.
摘要:
Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.
摘要:
Submersible media filters and submersible columns for use in removing radioactive isotopes and other contaminants from a fluid stream, such as a fluid stream from the primary coolant loop of a nuclear reactor system or a fluid stream from a spent-fuel pool. Generally, these submersible media filters and submersible columns are adapted to be submersed in the fluid stream, and additionally the filters are adapted to be vitrified after use, resulting in a stabilized, non-leaching final waste product with a substantially reduced volume compared to the original filter. In several embodiments, the submersible media filters and submersible columns include isotope-specific media (ISM).