Methods and systems are provided for continuous-flow production of radioisotopes with high specific activity. Radioisotopes with high specific activity produced according to the methods described are also provided. The methods can include causing a liquid capture matrix to contact a target containing a target nuclide; irradiating the target with radiation, ionizing radiation, particles, or a combination thereof to produce the radionuclides that are ejected from the target and into the capture matrix; and causing the liquid capture matrix containing the radionuclides to flow from the target to recover the capture matrix containing the radionuclides with high specific activity. The methods are suitable for the production of a variety of radionuclides. For example, in some aspects the target nuclide is .sup.237Np, and the radionuclide is .sup.238Np that decays to produce .sup.238Pu. In other aspects, the target nuclide is .sup.98Mo, and the radionuclide is .sup.99Mo that decays to produce .sup.99mTc.

An equatorial anthropic radiation source and a method of making an equatorial anthropic radiation source are described. The radiation source is useful in diagnostic imaging applications in healthcare or other industries (e.g. computerized three-dimensional segmental imaging; Crompton scattering imaging techniques; radiation detector check and calibration, in particular CdZnTe detectors commonly used in medical imaging).

An irradiation target for the production of radioisotopes, comprising at least one plate defining a central opening and an elongated central member passing through the central opening of the at least one plate so that the at least one plate is retained thereon, wherein the at least one plate and the elongated central member are both formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

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 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.

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.

An equatorial anthropic radiation source and a method of making an equatorial anthropic radiation source are described. The radiation source is useful in diagnostic imaging applications in healthcare or other industries (e.g. computerized three-dimensional segmental imaging; Crompton scattering imaging techniques; radiation detector check and calibration, in particular CdZnTe detectors commonly used in medical imaging).

An apparatus for processing a plurality of semiconductor wafers, the apparatus including a spallation chamber, a neutron producing material mounted in the spallation chamber, a neutron moderator, and an irradiation chamber coupled to the spallation chamber, wherein the neutron moderator is disposed between the spallation chamber and the irradiation chamber, wherein the irradiation chamber is configured to accommodate the plurality of semiconductor wafers, wherein each of the plurality of semiconductor wafers has a first surface and a second surface opposite the first surface, wherein the plurality of semiconductor wafers are positioned so that a first surface of one semiconductor wafer faces a second surface of another semiconductor wafer.

An apparatus for processing a plurality of semiconductor wafers, the apparatus including a spallation chamber, a neutron producing material mounted in the spallation chamber, a neutron moderator, and an irradiation chamber coupled to the spallation chamber, wherein the neutron moderator is disposed between the spallation chamber and the irradiation chamber, wherein the irradiation chamber is configured to accommodate the plurality of semiconductor wafers, wherein each of the plurality of semiconductor wafers has a first surface and a second surface opposite the first surface, wherein the plurality of semiconductor wafers are positioned so that a first surface of one semiconductor wafer faces a second surface of another semiconductor wafer.