Patent classifications
G21F1/06
Iron tungsten borocarbide body for nuclear shielding applications
Provided is a body, a method for manufacturing the body and a method of using of the body for nuclear shielding in a nuclear reactor. The body may include boron, iron, chromium, carbon and tungsten.
Iron tungsten borocarbide body for nuclear shielding applications
Provided is a body, a method for manufacturing the body and a method of using of the body for nuclear shielding in a nuclear reactor. The body may include boron, iron, chromium, carbon and tungsten.
Ceramic shielding apparatus
Disclosed is a ceramic shielding apparatus including at least one shield made of a ceramic material and provided inside or outside an X-ray tube to shield radiation; and supports configured to support the shield. According to such a configuration, disadvantages of conventional shielding materials such as lead can be addressed, so that a shield apparatus having excellent shielding properties while being harmless to the human body can be provided.
Ceramic shielding apparatus
Disclosed is a ceramic shielding apparatus including at least one shield made of a ceramic material and provided inside or outside an X-ray tube to shield radiation; and supports configured to support the shield. According to such a configuration, disadvantages of conventional shielding materials such as lead can be addressed, so that a shield apparatus having excellent shielding properties while being harmless to the human body can be provided.
COMBINATION OF CONTAINERS AND METHOD FOR ELIMINATING RADIOACTIVE SUBSTANCES
The invention relates to a combination of containers intended to discharge radioactive substances into the earth's magma by pouring them into lava lakes, and to a method for using these containers. The radioactive substances are preferably placed in ovoid waste containers that are loaded into a transport container and discharged therewith into a lava lake. The transport container decomposes by melting following a first immersion at a given depth and releases the waste containers, which continue to move downwards.
COMBINATION OF CONTAINERS AND METHOD FOR ELIMINATING RADIOACTIVE SUBSTANCES
The invention relates to a combination of containers intended to discharge radioactive substances into the earth's magma by pouring them into lava lakes, and to a method for using these containers. The radioactive substances are preferably placed in ovoid waste containers that are loaded into a transport container and discharged therewith into a lava lake. The transport container decomposes by melting following a first immersion at a given depth and releases the waste containers, which continue to move downwards.
Safety scavenge screen assembly
An apparatus includes a splash shield incorporating a clear viewing area, a vacuum manifold, the vacuum manifold adapted to releasably engage the splash shield, and a link emanating from the vacuum manifold, the link configured to attach to a vacuum system wherein application of a vacuum creates a laminar flow to draw vapor away from the splash shield.
Safety scavenge screen assembly
An apparatus includes a splash shield incorporating a clear viewing area, a vacuum manifold, the vacuum manifold adapted to releasably engage the splash shield, and a link emanating from the vacuum manifold, the link configured to attach to a vacuum system wherein application of a vacuum creates a laminar flow to draw vapor away from the splash shield.
Changing Density Particles Having a Neutron Absorbent and a Thermal Conductor
Composition, manufactures, and methods of making and using them, illustratively a process including the steps of: changing density of a composition including a neutron absorbent, the absorbent having a neutron absorption cross section greater than or equal to Boron comprising at least 19.7% of Boron-10 isotope, and a thermal conductor having a thermal conductivity of at least 10% of coolant thermal conductivity at 100 degrees C. at sea level, combined into the particles that have a density of at least 0.9982 g/mL and not more than 2.0 g/ml, the altering carried out in association with nuclear fuel or nuclear waste in a cask that is not located in a nuclear reactor containment vessel, the cask being a nuclear fuel cask or a spent nuclear fuel cask, the changing carried out by relocating the composition by at least one of the sub steps comprising: (A) operating a hollow conduit connected to a reservoir to relocate at least some of the particles from a reservoir into the cask, and/or (B) altering a close pack formation of the particles by effectuating a change from a static coefficient of friction of the particles to a dynamic coefficient of friction of the particles, thereby redistributing the particles within the cask into an altered close pack formation, and/or (C) removing at least some of the particles from the cask into the reservoir.
Changing Density Particles Having a Neutron Absorbent and a Thermal Conductor
Composition, manufactures, and methods of making and using them, illustratively a process including the steps of: changing density of a composition including a neutron absorbent, the absorbent having a neutron absorption cross section greater than or equal to Boron comprising at least 19.7% of Boron-10 isotope, and a thermal conductor having a thermal conductivity of at least 10% of coolant thermal conductivity at 100 degrees C. at sea level, combined into the particles that have a density of at least 0.9982 g/mL and not more than 2.0 g/ml, the altering carried out in association with nuclear fuel or nuclear waste in a cask that is not located in a nuclear reactor containment vessel, the cask being a nuclear fuel cask or a spent nuclear fuel cask, the changing carried out by relocating the composition by at least one of the sub steps comprising: (A) operating a hollow conduit connected to a reservoir to relocate at least some of the particles from a reservoir into the cask, and/or (B) altering a close pack formation of the particles by effectuating a change from a static coefficient of friction of the particles to a dynamic coefficient of friction of the particles, thereby redistributing the particles within the cask into an altered close pack formation, and/or (C) removing at least some of the particles from the cask into the reservoir.