Patent classifications
G01T7/02
Radiation image capturing apparatus, radiation image capturing system, and method of controlling radiation image capturing apparatus
A radiation image capturing apparatus is provided. The radiation image capturing apparatus includes an image capturing unit configured to capture a radiation image. The image capturing unit includes a detection element configured to detect radiation. The radiation image capturing apparatus comprises a processor configured to perform, in accordance with an exposure request from a user, a first reset operation of resetting the detection element, and configured to detect an amount of irradiation of the radiation based on a signal from the detection element after the first reset operation.
14C testing bottle, testing device and method, sampling and preparation system and method
A .sup.14C testing bottle, a .sup.14C testing device, a .sup.14C testing method, a sampling and preparation system and its implementation method are provided. The .sup.14C testing bottle includes a pressure-bearing shell and a sample bin positioned in the pressure-bearing shell. A cavity is arranged in the sample bin and the .sup.14C testing bottle is provided with an injection port connected to the cavity. The sample bin may diffuse the light produced in the cavity and at least part of the sample bin is transparent. An optical fiber channel is set on the pressure-bearing shell. One end of the optical fiber channel is connected with an external scintillation counter, and the other end of the optical fiber channel is connected with the transparent part of the sample bin. The .sup.14C testing bottle may measure the .sup.14C content in the carbon dioxide sample rapidly.
14C testing bottle, testing device and method, sampling and preparation system and method
A .sup.14C testing bottle, a .sup.14C testing device, a .sup.14C testing method, a sampling and preparation system and its implementation method are provided. The .sup.14C testing bottle includes a pressure-bearing shell and a sample bin positioned in the pressure-bearing shell. A cavity is arranged in the sample bin and the .sup.14C testing bottle is provided with an injection port connected to the cavity. The sample bin may diffuse the light produced in the cavity and at least part of the sample bin is transparent. An optical fiber channel is set on the pressure-bearing shell. One end of the optical fiber channel is connected with an external scintillation counter, and the other end of the optical fiber channel is connected with the transparent part of the sample bin. The .sup.14C testing bottle may measure the .sup.14C content in the carbon dioxide sample rapidly.
Sample container, sampling system, nuclear power plant and corresponding operating method
A sample container, sampling system and operating methods permit representative sampling from a liquid phase or boiling liquid, a gaseous phase, a containment sump, containment atmosphere, or condensation chamber of a nuclear power plant following a severe accident. A sample container obtaining an environmental sample includes an outer chamber surrounded by an outer container wall, being directly fluidically connected to the environment through a passage opening in the outer container wall and being fillable with a liquid at least in a base region. An inner chamber surrounded by an inner container wall is fluidically connected to the base region through a passage opening in the inner container wall, has connections for sampling and conveyor medium lines and is otherwise pressure and media tightly sealed from the environment. A pneumatically or hydraulically actuatable closure device for the passage opening between the outer and inner chambers has an actuation medium line connection.
Sample container, sampling system, nuclear power plant and corresponding operating method
A sample container, sampling system and operating methods permit representative sampling from a liquid phase or boiling liquid, a gaseous phase, a containment sump, containment atmosphere, or condensation chamber of a nuclear power plant following a severe accident. A sample container obtaining an environmental sample includes an outer chamber surrounded by an outer container wall, being directly fluidically connected to the environment through a passage opening in the outer container wall and being fillable with a liquid at least in a base region. An inner chamber surrounded by an inner container wall is fluidically connected to the base region through a passage opening in the inner container wall, has connections for sampling and conveyor medium lines and is otherwise pressure and media tightly sealed from the environment. A pneumatically or hydraulically actuatable closure device for the passage opening between the outer and inner chambers has an actuation medium line connection.
PET SYSTEM WITH A POSITRON LIFETIME MEASUREMENT FUNCTION AND POSITRON LIFETIME MEASUREMENT METHOD IN A PET SYSTEM
A PET system with a positron lifetime measurement function includes: a first gamma ray detector configured to receive, from an imaging target containing a nuclide that goes into an excited state of a daughter nucleus by undergoing beta decay and that then, subsequently to emission of a positron resulting from the beta decay, emits a deexcitation gamma ray when transiting into a ground state of the daughter nucleus, three annihilation gamma rays resulting from the positron annihilating with an electron, the first gamma ray detector thereby detecting the three annihilation gamma rays; a second gamma ray detector configured to detect the deexcitation gamma ray; and a processor configured to derive, in three dimensions, a distribution state of the nuclide in the imaging target and to determine information on a positron lifetime in association with a derived distribution position.
PET SYSTEM WITH A POSITRON LIFETIME MEASUREMENT FUNCTION AND POSITRON LIFETIME MEASUREMENT METHOD IN A PET SYSTEM
A PET system with a positron lifetime measurement function includes: a first gamma ray detector configured to receive, from an imaging target containing a nuclide that goes into an excited state of a daughter nucleus by undergoing beta decay and that then, subsequently to emission of a positron resulting from the beta decay, emits a deexcitation gamma ray when transiting into a ground state of the daughter nucleus, three annihilation gamma rays resulting from the positron annihilating with an electron, the first gamma ray detector thereby detecting the three annihilation gamma rays; a second gamma ray detector configured to detect the deexcitation gamma ray; and a processor configured to derive, in three dimensions, a distribution state of the nuclide in the imaging target and to determine information on a positron lifetime in association with a derived distribution position.
DOSIMETER CONTAINER AND DOSAGE MEASURING BODY
A dosimeter container comprising a housing portion and a shield portion that surrounds the housing portion is provided. The housing portion houses a radiation dosage measuring device for measuring a dosage of predetermined radiation other than neutron radiation. The shield portion is composed of a member made of a material that transmits predetermined radiation and shields neutron radiation. The shield portion is a LiF sintered body, in particular, a .sup.6LiF sintered body. Further, the shield portion includes at least two or more shield portion components (a body portion and a lid portion), in which adjacent members can abutt against each other. The housing portion is same size as or larger than the size of the radiation dosage measuring device; and the housing portion extends over the entirety of the components. The dosimeter container is preferably used as a dosage measuring body having a radiation dosage measuring device stored in the housing portion.
DOSIMETER CONTAINER AND DOSAGE MEASURING BODY
A dosimeter container comprising a housing portion and a shield portion that surrounds the housing portion is provided. The housing portion houses a radiation dosage measuring device for measuring a dosage of predetermined radiation other than neutron radiation. The shield portion is composed of a member made of a material that transmits predetermined radiation and shields neutron radiation. The shield portion is a LiF sintered body, in particular, a .sup.6LiF sintered body. Further, the shield portion includes at least two or more shield portion components (a body portion and a lid portion), in which adjacent members can abutt against each other. The housing portion is same size as or larger than the size of the radiation dosage measuring device; and the housing portion extends over the entirety of the components. The dosimeter container is preferably used as a dosage measuring body having a radiation dosage measuring device stored in the housing portion.
FIBER AND BUNDLE ORIENTATIONS, MATRIX RICH REGIONS, AND MECHANICAL PROPERTIES OF FIBER REINFORCED COMPOSITES USING THERMAL DIGITAL IMAGE CORRELATION
Methods for assessing fiber and bundle orientations and mechanical properties of fiber reinforced composite materials using Thermal Digital Image Correlation (TDIC) are disclosed. In some examples, the method comprises exposing the composite material to a temperature change; imaging the composite material at a plurality of time points before, during and/or after the temperature change; and assessing the characteristic of the composite material based on the imaging. In others, temperature changes naturally occur during the cooling process after manufacturing can be employed for this method such as compression molding process, injection molding process, resin transfer molding processes and its variants.