Disclosed herein are charge or electricity generating devices and methods of making and use thereof.

The present disclosure relates to an insoluble cesium mixed multimetal oxide, ceramic, glass-ceramic or glass which is intended to be a replacement for cesium chloride or similar materials used as radiation sources. Additionally, this insoluble compound could replace other insoluble lower specific activity cesium compounds used in industrial, underwater, and underground/downhole application because it would allow the use of older lower specific activity cesium stock solutions. The disclosure further provides a method for the cesium to be recovered from cesium chloride sources.

The present disclosure relates to an insoluble cesium mixed multimetal oxide, ceramic, glass-ceramic or glass which is intended to be a replacement for cesium chloride or similar materials used as radiation sources. Additionally, this insoluble compound could replace other insoluble lower specific activity cesium compounds used in industrial, underwater, and underground/downhole application because it would allow the use of older lower specific activity cesium stock solutions. The disclosure further provides a method for the cesium to be recovered from cesium chloride sources.

Provided herein is a method for fabricating a heat source for a radioisotope thermoelectric generator (RTG). The method may include reducing a particle size in a strontium compound by powdering and sieving the strontium compound and/or dissolving the strontium compound into an aqueous solution; mixing the strontium compound with graphite to obtain a strontium-graphite mixture; performing a press to the strontium-graphite mixture; and encapsulating the pressed strontium-graphite mixture into an x-ray shielding to obtain the heat source.

Provided herein is a method for fabricating a heat source for a radioisotope thermoelectric generator (RTG). The method may include reducing a particle size in a strontium compound by powdering and sieving the strontium compound and/or dissolving the strontium compound into an aqueous solution; mixing the strontium compound with graphite to obtain a strontium-graphite mixture; performing a press to the strontium-graphite mixture; and encapsulating the pressed strontium-graphite mixture into an x-ray shielding to obtain the heat source.

Provided is a process which allows uranium and molybdenum fluorides to be efficiently separated, said process comprising a step of providing a mixture containing MoF.sub.6 and UF.sub.6; a step of reducing the UF.sub.6 to UF.sub.5 in the gas phase or in a liquid phase; and a step of separating the UF.sub.5 and the MoF.sub.6 or a conversion product thereof which may be obtained by further converting the molybdenum fluoride to another molybdenum compound. In a further aspect, a process for the fluorination of metals or semimetals is provided.

Provided is a process which allows uranium and molybdenum fluorides to be efficiently separated, said process comprising a step of providing a mixture containing MoF.sub.6 and UF.sub.6; a step of reducing the UF.sub.6 to UF.sub.5 in the gas phase or in a liquid phase; and a step of separating the UF.sub.5 and the MoF.sub.6 or a conversion product thereof which may be obtained by further converting the molybdenum fluoride to another molybdenum compound. In a further aspect, a process for the fluorination of metals or semimetals is provided.

A nuclear battery module is adapted for a nuclear battery. The nuclear battery module includes a radioactive unit and at least one energy conversion unit. The radioactive unit includes a soft substrate and at least one radioactive layer disposed on the soft substrate. The at least one radioactive layer includes a -ray source. The at least one energy conversion unit includes a flexible carrier layer, an N-type semiconductor layer disposed on the flexible carrier layer, and a P-type semiconductor layer disposed on the N-type semiconductor layer opposite to the flexible carrier layer. The at least one energy conversion unit is disposed on the radioactive unit in a manner such that the flexible carrier layer is proximate to the radioactive unit.

A nuclear battery module is adapted for a nuclear battery. The nuclear battery module includes a radioactive unit and at least one energy conversion unit. The radioactive unit includes a soft substrate and at least one radioactive layer disposed on the soft substrate. The at least one radioactive layer includes a -ray source. The at least one energy conversion unit includes a flexible carrier layer, an N-type semiconductor layer disposed on the flexible carrier layer, and a P-type semiconductor layer disposed on the N-type semiconductor layer opposite to the flexible carrier layer. The at least one energy conversion unit is disposed on the radioactive unit in a manner such that the flexible carrier layer is proximate to the radioactive unit.

Means and method for photo-enhanced electro-catalytic process using nuclear thermal NTAC-integrated PEEC (PEEC-NTAC) catalytic processes combining ECM with energetic photon sources, such gamma rays, and sono-catalytic driver.