The disclosure relates to a device for checking a fuel rod comprising a testing container having first and second chambers, a first checking device arranged in the testing container, wherein the testing container has at least one inlet opening, at least one outlet opening, and an insertion opening for inserting the fuel rod into the second chamber, and wherein a valve is arranged in a connecting channel connecting the first and the second chamber. A method is disclosed for checking a fuel rod in a water-filled basin of a submerged nuclear plant having such a device, wherein the fuel rod is inserted into the second chamber of the testing container through the insertion opening while the valve is closed, wherein a fluid is fed in via the at least one inlet opening, and wherein the valve is opened in order to check the fuel rod with the first checking device.

A leakage testing device for testing leakage of a nuclear fuel assembly (18) by sipping, includes a collection assembly (32) that is configured to close an upper end (24A) of a cell (24) of a storage rack (22) for storing nuclear fuel assembly/ies (18) discharged from a nuclear reactor (4), so as to prevent water contained in the cell (24) from escaping via the upper end (24A) of the cell (24), and to collect products containing possible fission products released by a nuclear fuel assembly (18) contained in the cell (24).

A leakage testing device for testing leakage of a nuclear fuel assembly (18) by sipping, includes a collection assembly (32) that is configured to close an upper end (24A) of a cell (24) of a storage rack (22) for storing nuclear fuel assembly/ies (18) discharged from a nuclear reactor (4), so as to prevent water contained in the cell (24) from escaping via the upper end (24A) of the cell (24), and to collect products containing possible fission products released by a nuclear fuel assembly (18) contained in the cell (24).

The invention relates to a device for performing a leak test on a fuel rod capsule, which contains at least one fuel rod and test gas, which device comprises a test container, which is designed to accommodate at least one fuel rod capsule and can be lowered into a pool of a nuclear plant flooded with water. According to the invention, a mass spectrometer is fluidically connected to the interior of the test container in such a way that a gas flow can be fed to the mass spectrometer in order to sense the concentration of the test gas that has diffused into the test container from the fuel rod capsule.

The invention relates to a device for performing a leak test on a fuel rod capsule, which contains at least one fuel rod and test gas, which device comprises a test container, which is designed to accommodate at least one fuel rod capsule and can be lowered into a pool of a nuclear plant flooded with water. According to the invention, a mass spectrometer is fluidically connected to the interior of the test container in such a way that a gas flow can be fed to the mass spectrometer in order to sense the concentration of the test gas that has diffused into the test container from the fuel rod capsule.

A system for monitoring fissile material contents inside of a nuclear reactor can include at least a first neutron detector positioned outside a radiation shield and configured to detect a plurality of neutrons originating from the reactor core and having passed through the radiation shield, and configured to generate a first output signal, and a controller communicably linked to the first neutron detector to receive the first output signal and a power output of the nuclear reactor.

The single rod ultrasonic leak detection tool will be used to detect leaking fuel rods by evaluation if there is water inside the rod. The test will be performed by moving one fuel rod between two ultrasonic transducer oriented in a pitch/catch configuration. The detection tool uses ultrasonic transducers as the primary method to detect leaking fuel rods. Two probes are preferably positioned near the fuel rod in a pitch/catch or transmitting/receiving configuration. One probe 36 sends the signal into the rod and the other probe of a set of probes receives the signal. An evaluation of the received signal is performed in various embodiments, to determine leak tightness of the fuel rod. In various aspects, two sets of probes may be utilized so that measurements can be taken on both sides of the fuel rod.

The single rod ultrasonic leak detection tool will be used to detect leaking fuel rods by evaluation if there is water inside the rod. The test will be performed by moving one fuel rod between two ultrasonic transducer oriented in a pitch/catch configuration. The detection tool uses ultrasonic transducers as the primary method to detect leaking fuel rods. Two probes are preferably positioned near the fuel rod in a pitch/catch or transmitting/receiving configuration. One probe 36 sends the signal into the rod and the other probe of a set of probes receives the signal. An evaluation of the received signal is performed in various embodiments, to determine leak tightness of the fuel rod. In various aspects, two sets of probes may be utilized so that measurements can be taken on both sides of the fuel rod.

The disclosure relates to a device for checking a fuel rod comprising a testing container having first and second chambers, a first checking device arranged in the testing container, wherein the testing container has at least one inlet opening, at least one outlet opening, and an insertion opening for inserting the fuel rod into the second chamber, and wherein a valve is arranged in a connecting channel connecting the first and the second chamber. A method is disclosed for checking a fuel rod in a water-filled basin of a submerged nuclear plant having such a device, wherein the fuel rod is inserted into the second chamber of the testing container through the insertion opening while the valve is closed, wherein a fluid is fed in via the at least one inlet opening, and wherein the valve is opened in order to check the fuel rod with the first checking device.

A method and system detects failures in nuclear fuel assemblies (600). A water treatment device degasses/removes fission gases from water used in the canister (500) of a vacuum sipping device (30). A sipping procedure then detects a failure in a fuel assembly in the canister. The degassing improves a signal-to-noise ratio of the detector used during the sipping process, and improves the failure detection sensitivity of the system. Additionally and/or alternatively, gas may be recirculated through the canister water before the vacuum is applied so that fission gas concentration in the recirculating gas reaches a baseline equilibrium with the canister water. The vacuum is thereafter applied and the sipping procedure proceeds such that an increase in detected radioactivity over the baseline equilibrium indicates a leak in the fuel assembly.