An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and/or control patient infusion procedures.

Disclosed is a dose measuring device for the measurement of a radiation dose which comprises a radiation-sensitive measuring film and a base body, wherein the measuring film is wound onto the base body in some areas. Furthermore, a measurement method using such a dose measuring device is disclosed to determine the radiation dose applied during the pasteurization and/or sterilization of particulate material.

Disclosed is a dose measuring device for the measurement of a radiation dose which comprises a radiation-sensitive measuring film and a base body, wherein the measuring film is wound onto the base body in some areas. Furthermore, a measurement method using such a dose measuring device is disclosed to determine the radiation dose applied during the pasteurization and/or sterilization of particulate material.

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.

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.

A method of determining a quantity of a first radioisotope in a source term, disintegrating into a second radioisotope, the radioisotopes respectively emitting first and second gamma rays screened by the source term, the method comprising the steps: a) determining the theoretical ratio of counts between the first and second rays emitted in the absence of screening; b) measuring the net counts associated with the first and second rays emitted by the first and second radioisotopes; c) determining the screening rates of the first and second rays by the source term based on the ratio obtained in step a) and the counts obtained in step b); d) determining the quantity of the first radioisotope based on the screening rate of either the first or the second ray determined in step c).

A method of determining a quantity of a first radioisotope in a source term, disintegrating into a second radioisotope, the radioisotopes respectively emitting first and second gamma rays screened by the source term, the method comprising the steps: a) determining the theoretical ratio of counts between the first and second rays emitted in the absence of screening; b) measuring the net counts associated with the first and second rays emitted by the first and second radioisotopes; c) determining the screening rates of the first and second rays by the source term based on the ratio obtained in step a) and the counts obtained in step b); d) determining the quantity of the first radioisotope based on the screening rate of either the first or the second ray determined in step c).

According to the present invention, a laminate is disposed on a spacer in a bottle. The laminate comprises: a sample layer that includes a sample sheet; an upper scintillator layer (upper member); and a lower scintillator layer (lower member). Each of the upper and lower scintillator layers is made of a plastic scintillator material. The sample sheet is manufactured by laminating a carrier such as filter paper having a radioactive substance adhered thereto.

According to the present invention, a laminate is disposed on a spacer in a bottle. The laminate comprises: a sample layer that includes a sample sheet; an upper scintillator layer (upper member); and a lower scintillator layer (lower member). Each of the upper and lower scintillator layers is made of a plastic scintillator material. The sample sheet is manufactured by laminating a carrier such as filter paper having a radioactive substance adhered thereto.

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.