A nuclear system. The nuclear system includes a fuel rod for use in a nuclear reactor. The fuel rod includes a cladding comprising an interior region, unspent fuel pellets housed in the interior region of the cladding, and a resonant electrical circuit supported within the interior region of the cladding. The resonant electrical circuit is configured to receive an excitation pulse through the cladding, and responsive to the received excitation pulse, generate a response pulse in the form of a magnetic field signal that is structured to travel wirelessly from the interior region and through the cladding. The nuclear system also includes a receiver positioned outside of the cladding and within the nuclear reactor. The receiver is configured to receive the response pulse and generate an output based on the received response pulse.

A pressure gauge includes a case with a dial, and a pressure detection unit is located in the case. The chassis plate including a first pivot unit, a second pivot unit, a first Bourdon Tube, a second Bourdon Tube, a first transmission unit, a second transmission unit and an entrance connected thereto. The first Bourdon Tube is connected to the first pivot unit by the first transmission unit, and the second Bourdon Tube is connected to the second pivot unit by the second transmission unit. The entrance communicates with the first and second Bourdon Tubes. The first and second pivot units extend through the dial so as to be connected with a first hand and a second hand respectively. The first and second hands respectively respond different pressure values for more accuracy.

A pressure gauge includes a housing, a helical tube, and a compensation member. The housing has an inlet. The helical tube is arranged within the housing and has a closed end and an open end, the open end of the helical tube in fluid communication with the inlet. The compensation member is arranged between the between the open end and the closed end of the helical tube, the compensation member fixed to the helical tube. The compensation member and the helical tube are formed from materials having different coefficients of thermal expansion to limit movement of the closed end of the helical tube due to temperature change of a compressed fluid in fluid communication with the helical tube. Pressure vessel assemblies and methods of displaying pressure in pressure vessels are also described.

The invention relates to a density monitor (10) for monitoring a gas density in a gas chamber (20). The density monitor (10) comprises a measuring apparatus (12) having a first measuring device (24) and a second measuring device (28), the two measuring devices (24; 28) being coupled together. The first measuring device (24) is designed to measure a first pressure range (62) in relative terms with respect to an atmosphere, and the second measuring device (28) is configured to measure a second pressure range (64) in absolute terms. The density monitor (10) further comprises an indicator device (50), which is designed to indicate the two pressure ranges (24; 28). The density monitor (10) also comprises a movable drive element (48), which is designed to drive the indicator device (50), wherein at least one of the two measuring devices (24; 28) is designed to move the drive element (48) in order to drive the indicator device (50), wherein the indicator device (50) comprises an indicator element (58) which is designed to indicate the two pressure ranges (62, 64).

A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pure and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.

A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pulse and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.

The invention relates to a pressure gauge for measuring the pressure of a fluid, the pressure gauge being designed for a pressure range with a maximum pressure, with: a housing with a housing wall which is filled with a filling fluid; a pressure connection located in the housing wall; a tubular spring located in the housing and connected to the pressure connection, whereby a fluid can flow through the pressure connection into the tubular spring, whereby the tubular spring is designed to expand in the direction of the housing wall when pressure is applied by the fluid, thereby mechanically acting on an indicator to indicate the pressure of the fluid; and at least one volume reduction element which is at least partially located in the housing between the tubular spring and the housing wall in the direction of expansion of the tubular spring, whereby the at least one volume reduction element is an injection-molded plastic part.

Disclosed is a device that includes a housing attachable to a pressure gauge, and a pressure indicator manually pivotable within the housing to a set position. The housing is configured to enclose and retain the pressure indicator in the set position.

A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pulse and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.

A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pulse and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.