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 capsule for the transfer of a target material in a conveying system between a target irradiation station and a collecting station comprising: a beamline channel for the passage of an energetic beam irradiating the target material, a target holder holding the target material or a substrate backing the target material at a glancing angle with respect to the beamline channel axis, a degrader foil positioned across the beamline channel for degrading an energy of the energetic beam upstream of the target material, a target cooling inlet and a target cooling outlet for passage of a cooling fluid in a target cooling duct in a vicinity of the target holder such that the target material can be cooled during an irradiation, and a degrader foil cooling inlet and a degrader foil cooling outlet for passage of a cooling gas in a vicinity of the degrader foil.

The present disclosure is related to novel solid target systems that produce novel high-purity radionuclide compositions using medical cyclotrons, the compositions are of suitable radionuclidic and chemical purity for use in radiopharmaceutical applications, for example, diagnostic imaging and targeted-radionuclide therapy in nuclear medicine.

The present disclosure is related to novel solid target systems that produce novel high-purity radionuclide compositions using medical cyclotrons, the compositions are of suitable radionuclidic and chemical purity for use in radiopharmaceutical applications, for example, diagnostic imaging and targeted-radionuclide therapy in nuclear medicine.

Processes, apparatuses, and systems for the production, separation and purification of radioisotopes for medical, industrial, agricultural, and energy applications are disclosed. The following operations are performed: selective adsorption of at least one radionuclide to a solid support and desorption of the at least one absorbed radionuclide by evaporation; or electrochemical separation of the at least one radionuclide by electrochemically depositing either the at least one radionuclide or the target material on a metallic electrode; or removing the target material by high temperature sublimation under vacuum or in an inert atmosphere, if the at least one radionuclide is less volatile than the target material.

Processes, apparatuses, and systems for the production, separation and purification of radioisotopes for medical, industrial, agricultural, and energy applications are disclosed. The following operations are performed: selective adsorption of at least one radionuclide to a solid support and desorption of the at least one absorbed radionuclide by evaporation; or electrochemical separation of the at least one radionuclide by electrochemically depositing either the at least one radionuclide or the target material on a metallic electrode; or removing the target material by high temperature sublimation under vacuum or in an inert atmosphere, if the at least one radionuclide is less volatile than the target material.

Disclosed is a method for preparing a strontium-82/rubidium-82 generator. The method includes: filling a column volume with a sorbent made of hydrated tin (IV) oxide; passing through the column an initial solution with strontium-82 radionuclide, which also contains ions of stable isotopes of calcium and strontium; and washing out rubidium-82 with a saline solution of 0.9% sodium chloride. In order to achieve a breakthrough of strontium-82 or strontium-85 below permissible levels, 0.01 and 0.1 kBq per 1 MBq .sup.82Rb, respectively, when passing not less than 17 liters of saline solution through columns with a volume of not less than 1.6 cm.sup.3 and a dry sorbent weight of not less than 3.8 g, a specific activity of strontium-82 in the initial solution is not less than 90 GBq (2400 mCi) per mg of stable strontium cations for a generator with an activity of 3700 MBq (100 mCi).

Disclosed is a method for preparing a strontium-82/rubidium-82 generator. The method includes: filling a column volume with a sorbent made of hydrated tin (IV) oxide; passing through the column an initial solution with strontium-82 radionuclide, which also contains ions of stable isotopes of calcium and strontium; and washing out rubidium-82 with a saline solution of 0.9% sodium chloride. In order to achieve a breakthrough of strontium-82 or strontium-85 below permissible levels, 0.01 and 0.1 kBq per 1 MBq .sup.82Rb, respectively, when passing not less than 17 liters of saline solution through columns with a volume of not less than 1.6 cm.sup.3 and a dry sorbent weight of not less than 3.8 g, a specific activity of strontium-82 in the initial solution is not less than 90 GBq (2400 mCi) per mg of stable strontium cations for a generator with an activity of 3700 MBq (100 mCi).

One embodiment of the present invention relates to a production method of a .sup.226Ra target, a production method of .sup.225Ac, or an electrodeposition solution for producing a .sup.226Ra target, and the production method of a .sup.226Ra target includes 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.