There is disclosed a method of generating non-ionizing radiation, non-ionizing .sup.4He atoms, or a combination of both, the method comprising: contacting graphene materials with a source of deuterium; and aging the graphene materials in the source of deuterium for a time sufficient to generate non-ionizing radiation, non-ionizing .sup.4 1-le atoms. In one embodiment, graphene materials may comprise carbon nanotubes, such as nitrogen doped single walled or multi-walled carbon nanotubes. Unlike an alpha particle, the non-ionizing .sup.4He atoms generated by the disclosed method are a low energy particles, such as one having an energy of less than 1 MeV, such as less than 100 keV. Other non-ionizing radiation that can be generated by the disclosed process include soft x-rays, phonons or energetic electrons within the carbon material, and visible light.

There is disclosed a method of generating non-ionizing radiation, non-ionizing .sup.4He atoms, or a combination of both, the method comprising: contacting graphene materials with a source of deuterium; and aging the graphene materials in the source of deuterium for a time sufficient to generate non-ionizing radiation, non-ionizing .sup.4 1-le atoms. In one embodiment, graphene materials may comprise carbon nanotubes, such as nitrogen doped single walled or multi-walled carbon nanotubes. Unlike an alpha particle, the non-ionizing .sup.4He atoms generated by the disclosed method are a low energy particles, such as one having an energy of less than 1 MeV, such as less than 100 keV. Other non-ionizing radiation that can be generated by the disclosed process include soft x-rays, phonons or energetic electrons within the carbon material, and visible light.

An apparatus for producing Pb-212. The apparatus comprises an emanation box that comprises an emanation source comprising a porous non-reactive material. The emanation box receives at least one of Th-228 and Ra-224, wherein the at least one of Th-228 and Ra-224 decays to Rn-220 within the emanation box. The apparatus further includes a carrier gas feed coupled to the emanation box. The carrier gas feed directs an inert gas into the emanation box and the inert gas carries the Rn-220 out of the emanation box through a carrier gas exit port of the emanation box. The apparatus also includes one or more Rn-220 targets coupled to the carrier gas exit port. The carrier gas carries the Rn-220 from the emanation box to the one or more Rn-220 targets and the Rn-220 decays into Pb-212 within the one or more Rn-220 targets. The Pb-212 is directed into the Pb-212 collection container.

An apparatus for producing Pb-212. The apparatus comprises an emanation box that comprises an emanation source comprising a porous non-reactive material. The emanation box receives at least one of Th-228 and Ra-224, wherein the at least one of Th-228 and Ra-224 decays to Rn-220 within the emanation box. The apparatus further includes a carrier gas feed coupled to the emanation box. The carrier gas feed directs an inert gas into the emanation box and the inert gas carries the Rn-220 out of the emanation box through a carrier gas exit port of the emanation box. The apparatus also includes one or more Rn-220 targets coupled to the carrier gas exit port. The carrier gas carries the Rn-220 from the emanation box to the one or more Rn-220 targets and the Rn-220 decays into Pb-212 within the one or more Rn-220 targets. The Pb-212 is directed into the Pb-212 collection container.

One embodiment of the present invention relates to a production method of .sup.225Ac includes; a production step of a .sup.226Ra target including an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using an electrodeposition solution that contains .sup.226Ra ions and a pH buffer, and an irradiating step of irradiating the .sup.226Ra target with at least one selected from charged particles, photons, and neutrons.

A method for evaluating a structure is disclosed, the structure including a base material containing at least one kind of metal selected from the group consisting of hydrogen storage metals and hydrogen storage alloys, an intermediate layer provided on the base material and stacked alternately with a first layer containing low work function substances relatively lower in work function than the metal and a second layer containing the metal, and a surface layer provided on the intermediate layer and containing the metal, wherein the method includes measuring a change in polarization between incident light and reflected light by irradiating the surface layer with light, while holding the structure at a predetermined temperature, and comparing a measurement value of the change in polarization with a threshold of a change in polarization of a structure prepared in advance and evaluating a soundness of the structure based on comparison results.

A method for evaluating a structure is disclosed, the structure including a base material containing at least one kind of metal selected from the group consisting of hydrogen storage metals and hydrogen storage alloys, an intermediate layer provided on the base material and stacked alternately with a first layer containing low work function substances relatively lower in work function than the metal and a second layer containing the metal, and a surface layer provided on the intermediate layer and containing the metal, wherein the method includes measuring a change in polarization between incident light and reflected light by irradiating the surface layer with light, while holding the structure at a predetermined temperature, and comparing a measurement value of the change in polarization with a threshold of a change in polarization of a structure prepared in advance and evaluating a soundness of the structure based on comparison results.

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

Methods of performing targeted alpha therapy of a cancer patient utilizing actinium-225, methods of preparing a targeted alpha therapy drug that includes actinium-225, methods of preparing actinium-225 from radium-226, and methods of recovering radium-226 from an aqueous produced material stream generated from a natural resource extraction process. The methods of recovering radium-226 include separating the radium-226 from the produced material stream to generate recovered radium-226. The methods of preparing actinium-225 include converting the recovered radium-226 into actinium-225. The methods of preparing the targeted alpha therapy drug include incorporating the actinium-225 into the targeted alpha therapy drug. The methods of performing targeted alpha therapy include treating the cancer patient with the targeted alpha therapy drug.