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 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.

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.

One embodiment provides a multi-segment rod that includes a plurality of rod segments. The rod segments are removably mated to each other via mating structures in an axial direction. An irradiation target is disposed within at least one of the rod segments, and at least a portion of at least one mating structure includes one and/or more combinations of neutron absorbing materials.

A decay station includes a housing comprising a radiation shielding. The housing delimits a decay conduit intended for containing the irradiation targets in the predetermined linear order. The decay conduit includes a decay conduit inlet, intended to be connected to the structure of the core of the nuclear reactor for receiving the irradiation targets therefrom; and a decay conduit outlet, intended to be connected to an irradiation target discharge system for discharging the irradiation targets from the decay station. The decay station further includes an inlet distributor, located at the decay conduit inlet, and configured for releasing only a predetermined amount of irradiation targets at a time from the decay station towards the structure of the core of the nuclear reactor. The inlet distributor is configured for releasing the irradiation targets closest to the decay conduit inlet, while retaining the remaining irradiation targets in the decay conduit. The decay station further includes an inlet counter configured for counting the number of irradiation targets entering or exiting the decay conduit through the decay conduit inlet. The inlet counter is located at the decay conduit inlet. The decay station further includes an outlet radiation detector configured for measuring the radiation emitted by an irradiation target located at the decay conduit outlet.

A decay station includes a housing comprising a radiation shielding. The housing delimits a decay conduit intended for containing the irradiation targets in the predetermined linear order. The decay conduit includes a decay conduit inlet, intended to be connected to the structure of the core of the nuclear reactor for receiving the irradiation targets therefrom; and a decay conduit outlet, intended to be connected to an irradiation target discharge system for discharging the irradiation targets from the decay station. The decay station further includes an inlet distributor, located at the decay conduit inlet, and configured for releasing only a predetermined amount of irradiation targets at a time from the decay station towards the structure of the core of the nuclear reactor. The inlet distributor is configured for releasing the irradiation targets closest to the decay conduit inlet, while retaining the remaining irradiation targets in the decay conduit. The decay station further includes an inlet counter configured for counting the number of irradiation targets entering or exiting the decay conduit through the decay conduit inlet. The inlet counter is located at the decay conduit inlet. The decay station further includes an outlet radiation detector configured for measuring the radiation emitted by an irradiation target located at the decay conduit outlet.

An irradiation target is formed into a sphere. The spherical irradiation target can be iridium metal containing natural or enriched iridium. The radiation source can be manufactured by manufacturing a spherical irradiation target, accommodating the spherical irradiation target in a rotating capsule, and rotating an axial flow impeller by a downward flow of a reactor primary coolant, whereby the rotating capsule is rotated. This radiation source provides an improved nondestructive inspection image having a high geometric resolution, and has no radiation source anisotropy and also has high target recyclability.

An irradiation facility for a nuclear reactor, a method of removing thermal heat from an irradiated object and adjusting an energy distribution/neutron/gamma-ray flux ratio of irradiation, and a product obtainable by the method.

A process of fusing common hydrogen to: (1) form all of the elements in the Periodic Table of Elements; and, (2) produce excess energy. The process involves controllably initiating the process of electron capture with a hydrogen nucleus, which produces virtual neutrons and a new short-lived negatively charged particle (Negatron).

A process of fusing common hydrogen to: (1) form all of the elements in the Periodic Table of Elements; and, (2) produce excess energy. The process involves controllably initiating the process of electron capture with a hydrogen nucleus, which produces virtual neutrons and a new short-lived negatively charged particle (Negatron).