Abstract: A laser wake-field acceleration (LWFA)-based nuclear fission system and related techniques are disclosed. In accordance with some embodiments, the disclosed system may be configured to accelerate charged particles, such as protons, to velocities close to the speed of light utilizing LWFA. The system also may be configured, in accordance with some embodiments, to use these high-energy relativistic charged particles in causing nuclear fission of a given downstream fissionable target, thereby releasing large amounts of harvestable energy. Optionally, the system further may be configured, in accordance with some embodiments, to utilize charged particles resulting from the fission in producing electrical energy.

Abstract: A laser wake-field acceleration (LWFA)-based nuclear fission system and related techniques are disclosed. In accordance with some embodiments, the disclosed system may be configured to accelerate charged particles, such as protons, to velocities close to the speed of light utilizing LWFA. The system also may be configured, in accordance with some embodiments, to use these high-energy relativistic charged particles in causing nuclear fission of a given downstream fissionable target, thereby releasing large amounts of harvestable energy. Optionally, the system further may be configured, in accordance with some embodiments, to utilize charged particles resulting from the fission in producing electrical energy.

Abstract: A ground-disposable module for encapsulating radioactive waste contained within shipping containers is disclosed herein. Generally, the modules comprise a rigid outer container for providing a first radiation and water barrier for the waste, an inner container formed from the shipping container for providing a second radiation and water barrier, and a central layer of grout which forms still another radiation and water barrier and which provides the rigid outer container with a substantially solid interior which reinforces the compressive strength of the module. The rigid outer container may hold a plurality of shipping containers which have been compacted. Such compaction maximizes the number of containers which may be encapsulated into a particular module, and increases the overall compressive strength of the module by increasing the integrity and strength of the shipping containers and wastes grouted therein.

Abstract: A land disposal site for the disposal of nuclear waste is disclosed which generally comprises a trench, a non-rigid, water-shedding cap formed from alluvium and silt which overlies this depression, and a solid array of waste-containing modules disposed in the trench for both encapsulating the waste and for supporting the non-rigid cap over the depression. The floor of the trench preferably includes a capillary barrier formed from a layer of gravel so that ground water will not seep up into the modules buried within the disposal site. The top surfaces of the modules are covered with a sloped layer of alluvium, which in turn is covered with another capillary barrier of gravel. This capillary barrier of gravel carries a sloped layer of silt which sheds running surface water and directs it into a pair of drains disposed on either side of the trench.

Abstract: A nuclear waste packaging facility for receiving both contact and remote handled nuclear waste in portable shipping containers and encapsulating this waste into ground-disposable modules is disclosed herein. The facility generally comprises a separately shielded section for processing remote handled waste including various remotely-controlled winches and conveyors, as well as a second, separately shielded section for processing contact handled waste. A module transportation and loading section is disposed between the remote and contact handled waste sections of the facility, and places empty module containers in a loading position adjacent each of the two, separately shielded sections of the facility. Both the contact and remote handled waste sections include radiation and ultrasonic detectors for determining the radioactive level of the waste, and whether or not any of this waste is in liquid form.

Abstract: The present invention provides a method for reducing the amount of hydrogen chloride contained in a gas stream by reacting the hydrogen chloride with ammonia in the gas phase so as to produce ammonium chloride. The combined gas stream is passed into a condensation and collection vessel and a cyclonic flow is created in the combined gas stream as it passes through the vessel. The temperature of the gas stream is reduced in the vessel to below the condensation temperature of ammonium chloride in order to crystallize the ammonium chloride on the walls of the vessel. The cyclonic flow creates a turbulence which breaks off the larger particles of ammonium chloride which are, in turn, driven to the bottom of the vessel where the solid ammonium chloride can be removed from the vessel. The gas stream exiting from the condensation and collection vessel is further cleaned and additional ammonium chloride is removed by passing through additional filters.