A neutron producing target is irradiated with a deuteron beam accelerated by a deuteron accelerator to generate neutrons, and first samples are directly irradiated with the fast neutrons produced in the neutron producing target. The fast neutrons, which have initially been scattered by a nuclear reaction in the first samples and have passed through the first samples, are multi-scattered by a neutron scattering material made of a light element disposed around the neutron producing target and the first samples to generate, by a nuclear reaction with the first samples and second samples, various radioisotopes in large amounts at the same time from the first samples and the second samples. Thereby, a new RI production technology can generate various radioisotopes in large amounts at the same time.

A method for purifying lutetium includes providing a solid composition comprising ytterbium and lutetium and subliming or distilling ytterbium from the solid composition at a temperature of about 1196° C. to about 3000° C. to leave a lutetium composition comprising a higher weight percentage of lutetium than was present in the solid composition.

An irradiation target system having an irradiation target with at least one annular plate defining a central opening and including an elongated body, a flange portion, and a tab portion, wherein the flange portion extends beyond a first end of the plurality of plates, a target debundling tool, having a base plate, a gripper assembly affixed to the base plate, and a twister assembly including a housing defining a target bore configured to receive the target therein, and a slide portion that is slidably and non-rotatably mounted to the housing at a bottom end of the target bore.

The present invention is directed to processes for ionizing one or more lanthanide isotopes, processes for separating lanthanide isotopes, various apparatus and systems useful for these processes, and compositions prepared from these processes.

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.

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 producing 225.sup.A including: a method (X) for purifying a .sup.226Ra-containing solution, including an adsorption step of allowing a .sup.226Ra ion to adsorb onto a carrier having a function of selectively adsorbing a divalent cation by bringing a .sup.226Ra-containing solution into contact with the carrier under an alkaline condition, and an elution step of eluting the .sup.226Ra ion from the carrier under an acidic condition; a method for producing a .sup.226Ra target, including an electrodeposition liquid preparation step of preparing an electrodeposition liquid by using a purified .sup.226Ra-containing solution obtained by the method (X), and an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using the electrodeposition liquid; and a step of irradiating a .sup.226Ra target produced by the method for producing a .sup.226Ra target with at least one selected from a charged particle, a photon, and a neutron by using an accelerator.

A method for producing 225.sup.A including: a method (X) for purifying a .sup.226Ra-containing solution, including an adsorption step of allowing a .sup.226Ra ion to adsorb onto a carrier having a function of selectively adsorbing a divalent cation by bringing a .sup.226Ra-containing solution into contact with the carrier under an alkaline condition, and an elution step of eluting the .sup.226Ra ion from the carrier under an acidic condition; a method for producing a .sup.226Ra target, including an electrodeposition liquid preparation step of preparing an electrodeposition liquid by using a purified .sup.226Ra-containing solution obtained by the method (X), and an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using the electrodeposition liquid; and a step of irradiating a .sup.226Ra target produced by the method for producing a .sup.226Ra target with at least one selected from a charged particle, a photon, and a neutron by using an accelerator.

A method of making Lu-177 involving dissolving enriched Yb.sub.2O.sub.3, loading dissolved enriched Yb.sub.2O.sub.3 on a first guard column containing resin prepared from (2-ethyl-1-hexyl)phosphonic acid mono(2-ethyl-1-hexyl)ester (HEH[EHP]), passing a first separation of a stream exiting from first guard column through a first resin cartridge containing dipentyl pentylphosphonate, collecting Lu-177 onto a first collection column having resin containing tetraoctyl diglycolamide (DGA), loading an exiting stream from first collection column on a second guard column containing resin prepared from (2-ethyl-1-hexyl)phosphonic acid mono(2-ethyl-1-hexyl)ester (HEH[EHP]); passing a first separation of a stream exiting from second guard column through a second resin cartridge containing dipentyl pentylphosphonate; collecting Lu-177 onto a second collection column having resin containing DGA; passing a second separation of a stream exiting from second guard column through a third resin cartridge containing dipentyl pentylphosphonate; and collecting Lu-177 having passed through the third resin cartridge onto a third collection column having resin containing DGA.

A method for the manufacture of Actinium-225 from a Radium-226 containing material. Radium-226 containing starting target material is shielded with a thermal neutron absorption shield and is subjected to neutron irradiation from a moderated nuclear reactor. Radium-226 is thereby converted into Radium-225 to provide a Radium-225-containing material. The Radium-225 in the Radium-225 containing material is allowed to decay into Actinium-225, and the Actinium-225 is isolated from the Radium-225 containing material. The neutron absorption shield shields the starting target material from neutrons having an energy in the range of 20 eV to 1000 eV.