A neutron activator includes a neutron source and a reflector-moderator. The neutron source has a housing extending along a longitudinal axis (B). A metallic target as part of the neutron source is provided to produce neutrons through the interaction with a proton beam, the metallic target having a plurality of plates arranged transversally with respect to the longitudinal axis (B). The neutron source also includes a cooling circuit to cool the metallic target. The reflector-moderator has an activation area configured to accommodate the neutron source and the material to be activated.

A hybrid nuclear reactor for producing a medical isotope includes an ion source for producing an ion beam from a gas, a target chamber including a target that interacts with the ion beam to produce neutrons, and an activation cell positioned proximate the target chamber and including a parent material that interacts with the neutrons to produce the medical isotope via a fission reaction.

An exposure method includes loading a first substrate on a loading portion , the first substrate having a photo alignment agent which is coated on the first substrate, irradiating the first substrate by moving the first substrate in a first speed in a first direction to a working portion while loading a second substrate on the loading portion, the working portion having an ultra violet light source generating ultra violet ray to harden a photo alignment agent, simultaneously irradiating the first substrate and the second substrate by moving the first substrate and the second substrate in the first direction in the working portion, and unloading the first substrate from an unloading portion while irradiating the second substrate by moving the second substrate in the first direction in the working portion.

One object is to provide an electron beam sterilization apparatus including: an inner-surface sterilization chamber (5) including an inner-surface electron beam application device; and a blocking chamber (6) for receiving a preform product (P) from the inner-surface sterilization chamber (5) and blocking X-rays produced by application of the electron beam. The blocking chamber (6) includes an upstream opening (62) and a downstream opening (63) formed therein, the preform product (P) being received through the upstream opening (62) and transferred through the downstream opening (63). The blocking chamber (6) includes: a gripper (74) for gripping the preform product (P); a sterilized rotation table (71) for conveying the gripped preform product (P) in a circular path; and a blocking wall (81) not in contact with the sterilized rotation table (71) and configured to block the X-rays.

An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

Provided is a target plate for radioisotope production that has sufficient durability and sufficient heat resistance for use in radioisotope production and that is capable of reducing the extent of radioactivation. In a target plate for radioisotope production, a support substrate, which supports a target, includes a graphite film(s). The thermal conductivity in a surface direction of the graphite film(s) is 1200 W/(m.Math.K) or greater, and the thickness of the graphite film(s) is 0.05 μm or greater and 100 μm or less.

Provided is a target plate for radioisotope production that has sufficient durability and sufficient heat resistance for use in radioisotope production and that is capable of reducing the extent of radioactivation. In a target plate for radioisotope production, a support substrate, which supports a target, includes a graphite film(s). The thermal conductivity in a surface direction of the graphite film(s) is 1200 W/(m.Math.K) or greater, and the thickness of the graphite film(s) is 0.05 μm or greater and 100 μm or less.

A system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging and delivering the target cell apparatus into a target station apparatus; a target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus; and (iii) the receiving cell apparatus and the dissolution/purification module.

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.