Abstract:
Apparatus for amplifying low level signals within a nuclear plant's containment building, derived from the ex-core nuclear instrumentation system. The system employs vacuum micro-electronic devices in place of conventional pre-amplifier assemblies to position the pre-amplifier assemblies closer to and within the vicinity of the ex-core detector outputs.
Abstract:
An in-core neutron monitor that employs vacuum microelectronic devices to configure an in-core instrument thimble assembly that monitors and wirelessly transmits a number of reactor parameters directly from the core of a nuclear reactor without the use of external cabling. The in-core instrument thimble assembly is substantially wholly contained within an instrument guide tube within a nuclear fuel assembly.
Abstract:
An in-core nuclear detector for detecting the neutron population surrounding the detector. The detector is an ion chamber having a cylindrical outer electrode that is insulated from a central electrode and capped to contain an Argon gas. An electron radiator that produces prompt neutron capture gamma radiation that is substantially, directly proportional to the local neutron population is disposed between the outer tubular electrode and the central electrode.
Abstract:
A long-lifespan in-core instrument having an extended lifespan due to an enhanced combustion lifespan of an emitter according to the present invention comprises: a central tube; an outer sheath tube distanced from the outer circumferential surface of the central tube; self-powered neutron detectors placed between the central tube and outer sheath tube, and each comprising an emitter of a material having a reaction cross section with neutron that is comparatively smaller than that of rhodium; a background detector for compensating for the background noise signal; core exit thermocouples for detecting the core exit temperature; and filler wires filling in the space between the self-powered neutron detectors, background detector and core exit thermocouples, and as such, the present invention can markedly reduce the amount of spent in-core instrument waste, which is high-level radioactive material, and thus can contribute in securing a utility space for the high-level waste material, as well as in reducing radiation exposure of the nuclear power plant personnel.
Abstract:
A traveling reactor power monitoring system includes a traveling reactor power monitoring system including a drive control unit configured to move a traveling probe in a guide tube by rotating a motor, and a proximity switch that generates a I stpreventing retraction signal when the travelling probe is detected by the proximity switch to exist at a predefined stop range in a shielding vessel. The drive control unit stops retracting the travelling probe when the 1 stpreventing retraction signal is generated by the proximity switch, and wipes out the 1 stpreventing retraction signal by detecting that the probe exists outside the predefined stop range on the basis of a probe information as a substitute for the 1 st preventing retracting signal output by the proximity switch.
Abstract:
The apparatus includes two or more electrical conductors, one or more signal devices, an analyzer and a time-domain reflectometer. The one or more signal devices may be adapted to apply one or more signals to the two or more electrical conductors and receive one or more signals from the two or more electrical conductors. The analyzer is adapted to determine power level in the nuclear reactor using at least one of the applied signals and at least one of the received signals. The method of determining power level in a nuclear reactor includes: measuring impedance values of two or more electrical conductors disposed in the nuclear reactor and using the measured impedance values to determine the power level.
Abstract:
A self-powered neutron detector having an emitter with a slightly negative bias voltage that assures that an increase in the electrons that enter the insulator are counted and decreases or eliminates the gamma induced prompt signal. Variations in the size of the bias is used as a diagnostic tool to estimate the gamma induced prompt signal.
Abstract:
A method to perform signal validation for either reactor fixed incore detectors and/or core exit thermocouples to enhance core monitoring systems. The method uses a combination of both measured sensor signals and expected signal responses to develop a ratio of measured to expected signals. The ratios are evaluated by determining the expected ratios for each detector based on the behavior of the remaining collection of detectors, taking into account the geometry/location of the other detectors. The method also provides for automatic removal of invalid detectors from the core power distribution determination if sufficient detectors remain on line to adequately characterize the core's power distribution.
Abstract:
The invention relates to a device (14) for the automated application of a lubricant (16) inside a pipeline (18). According to the invention, the device (14) comprises to this end: a supply line (22) for a transport gas (24) connected to the pipeline (18), into which supply line a connecting piece (31) is connected as a T-junction or 4-way junction (32); a transverse line (34) connected to this connecting piece (31), which transverse line encloses a lubricant plunger (36) which can be moved along the line longitudinally; and a lubricant reservoir (56) connected to the transverse line (34), wherein the lubricant plunger (36) is sealed at the outer circumference thereof against the transverse line (34). The lubricant plunger has a depression (50) to accept a portion of lubricant (16). The plunger can be moved from a load position (58) into a delivery position (60). In the load position (58), the depression (50) communicates with the lubricant reservoir (56) and, in the delivery position (60), the depression is arranged inside the connecting piece (31) where the transport gas (24) flowing into the pipeline (18) can flow over it.