A device for treating air with alpha radioisotope ionization, comprising a frame having an internal surface, the internal surface defining an internal space, a pair of internal brackets arranged within the internal space and removably connected to the frame, each internal bracket arranged to have at least one spacer arranged between the respective bracket and the internal surface of the frame, and at least one alpha ionizing apparatus removably connected to the pair of internal brackets.

A device for treating air with alpha radioisotope ionization, comprising a frame having an internal surface, the internal surface defining an internal space, a pair of internal brackets arranged within the internal space and removably connected to the frame, each internal bracket arranged to have at least one spacer arranged between the respective bracket and the internal surface of the frame, and at least one alpha ionizing apparatus removably connected to the pair of internal brackets.

A true random number generator is presented that includes a CMOS matrix detector with a top surface. A shell is positioned over the top surface, and the shell includes a radiation source and a luminophore or scintillator constructed to emit photons towards the top surface when the luminophore or scintillator is struck by electrons from the radioactive decay of the source of the radiation. The CMOS detector matrix is constructed to detect the photons emitted from the luminophore or scintillator and to produce a signal for the detected photons. The signal is communicated to a processor that produces true random numbers based on the signal from the detected photons.

The system for storage includes spent nuclear fuel arranged in a drift and at least one first mechanical structure configured to cause a target material to move in the drift. The at least one first mechanical structure is configured to at least assist in actively controlling an exposure rate of the target material to the spent nuclear fuel while the target material is being exposed to the spent nuclear fuel. The system includes at least one second mechanical structure configured to remove the target material from the drift after the target material is exposed to the spent nuclear fuel.

The system for storage includes spent nuclear fuel arranged in a drift and at least one first mechanical structure configured to cause a target material to move in the drift. The at least one first mechanical structure is configured to at least assist in actively controlling an exposure rate of the target material to the spent nuclear fuel while the target material is being exposed to the spent nuclear fuel. The system includes at least one second mechanical structure configured to remove the target material from the drift after the target material is exposed to the spent nuclear fuel.

Surrogate materials are in the form of solid particles that include surrogate isotopes, namely, short-lived isotopes selected and formed to serve as surrogates for the radioactive materials of a nuclear fallout without including isotopes that are, or that decay to, biologically or environmentally deleterious and persistent isotopes. The surrogate material may be formed using high-purity reactant material and irradiation and separation techniques that enable tailoring of the isotopes and ratios thereof included in the surrogate material, and the surrogate material may be dispersed, e.g., in a training environment, in solid form.

Surrogate materials are in the form of solid particles that include surrogate isotopes, namely, short-lived isotopes selected and formed to serve as surrogates for the radioactive materials of a nuclear fallout without including isotopes that are, or that decay to, biologically or environmentally deleterious and persistent isotopes. The surrogate material may be formed using high-purity reactant material and irradiation and separation techniques that enable tailoring of the isotopes and ratios thereof included in the surrogate material, and the surrogate material may be dispersed, e.g., in a training environment, in solid form.

The present disclosure provides a gamma-ray attenuator and a gamma-ray shield for use in gamma-ray spectroscopy. The gamma-ray attenuator is a sleeve comprising a wall, a distal end, and a proximal end. The distal end of the sleeve is closed, and the proximal end of the sleeve forms an opening. A copper insert, a tin insert and a tungsten insert are installed in the sleeve such that the copper insert is adjacent to the distal end and the tungsten insert is closest to the proximal end. The sleeve is comprised of one or more materials that do not substantially attenuate gamma-rays. The open end of the sleeve fits over a tungsten safe that is operable to hold a radionuclide sample. When fitted together, a gamma-ray attenuator and a safe comprise a gamma-ray shield.

A method for improving the heat sealability of a packaging material and a method for manufacturing a heat-sealed container or package are described. The material can be polymer-coated packaging paper or cardboard, or a polymeric packaging film. The material includes a polymer layer that contains polyester, particularly polylactide, the heat sealability of which is improved by ultraviolet radiation. Polylactide is useful as such or when blended, for example, with other biodegradable polyester. The containers and packages thus manufactured include disposable drinking cups and cardboard carton and box packages.

A method of excitation transfer to a radioactive source is provided, the radioactive source having a natural radioactive decay rate. The method includes: energizing a stimulatory device coupled to a radioactive source, thereby exciting the radioactive source to decay at an enhanced rate that is higher than the natural radioactive decay rate. An excitation transfer apparatus includes: a support element; a radioactive source mounted on the support element, the radioactive source having a natural radioactive decay rate; a stimulatory device coupled to the support element; and a driver operatively connected to the stimulatory device to energize the stimulatory device, wherein upon energization, the stimulatory device excites the radioactive source which thereby decays at an enhanced rate that is higher than the natural radioactive decay rate.