KR810000193B1 - Apparatus fo locating detective muclear fuel elements - Google Patents

Abstract

An ultrasonic search unit for testing nuclear fuel elements to detect the presence of water in fuel elements spaced within a fuel assembly used in a water cooled nuclear reactor is composed of a strip carrier, an ultrasonic transducer element disposed within the aperture with one of the electrodes and means for grounding the ultrasonic transducer element to the strip carrier. The unit is capable of freely traversing the restricted spaces between the fuel elements.

Description

Device to detect incomplete nuclear fuel body

1 is a front view of the detection apparatus of the present invention.

FIG. 2 is a bottom view of a portion of the device shown in FIG. 1;

3 is a schematic diagram illustrating the reverberation of ultrasonic radial pulses in a gas-filled nuclear fuel body using the apparatus shown in FIG.

4 is an oscillogram of pulses and reflections that characterize the reaction of a gas-filled nuclear fuel body in FIG.

FIG. 5 is a schematic diagram illustrating the reverberation of ultrasonic radial pulses in an incomplete nuclear fuel body filled with water using the apparatus shown in FIG.

6 is an oscillogram of pulses and reflections characterizing the reaction of a nuclear fuel body filled with water of FIG.

FIG. 7 is an oscillogram of pulses and reflections characterizing the reaction of a water-filled nuclear fuel body with a plenum spring located below it.

The present invention relates to a device for detecting an incomplete nuclear fuel body of a nuclear reactor. In a water-cooled heterogeneous reactor, a number of elongated fuel assemblies and control element injection tubes are densely arranged in a unified structure called a fuel assembly. The reactor core is generally composed of a grid of nuclear fuel assemblies arranged vertically. Each of the long, elongated nuclear fuel cells, characterized by fuel rods, tubes, fins, etc., is selectively capped and covered with a thin sheath, preventing fuel erosion and fission products from being released into the reactor coolant. Aluminum, aluminum alloys, stainless steel and zirconium are typical coating materials. The plenum chamber and clearance control the fission product gas released from the fuel, control the specific temperature expansion between the cladding and the fuel, and control the density change of the fuel during combustion. Is installed. The plenum is generally located at the end of the fuel body, which contains the plenum spring that supports the fuel in a fixed relationship.

In some cases, the fuel body is initially pressurized with a gas, typically helium gas, to minimize the extension of the cladding clip during long operation at high pressure in the reactor cooling system. The coating of the nuclear fuel body is designed to withstand the effects of the reactor's operation, including the effects of coolant hydraulic pressure, reactor temperature and pressure, nuclear fission gas pressure and fuel expansion and irradiation growth. If the coating breaks, the radioactive fission product leaks into the coolant or moderator, which is expected to occur during the operation of the reactor. It is desirable and necessary to be able to detect and replace incomplete or "failed" fuel cells, even if a purge is installed to remove the maximum amount of radioactivity expected to be generated due to flaws in the coating. Therefore, it is important to have a reliable means of detecting incomplete fuel bodies.

On the other hand, detecting incomplete fuel assemblies in a fuel assembly is difficult because the assembly is a radioactive material and has hundreds of closely arranged nuclear fuel bodies and injection tubes. However, disassembling and assembling a large number of fuel assemblies examined is not only a waste of time, but also results in damage to the fuel assembly. In reactors using liquid coolants, many installations and technologies have been proposed to detect incomplete fuel bodies in fuel assemblies based on vibration detection and decomposition, temperature differences, and ultrasonic phenomena. In these advanced technologies, detectors and techniques have generally relied on disassembling only a fraction of the fuel assembly. In addition, these technologies have relied more and more on the thermodynamic state changes of liquids leaking into incomplete nuclear fuel bodies, such as boiling, liquefaction, or both. In order to facilitate the detection of incomplete fuel assemblies in fuel assemblies, there has been a demand for the development of reliable devices that do not rely on disassembling fuel assemblies or relying on the boiling or liquefaction of liquids within them.

According to the present invention, an apparatus for detecting an incomplete fuel assembly is installed in a fuel assembly of the type described above.

The ultrasonic search apparatus manufactured by the present invention is inserted into the space between the fuel assembly parts. The smallest space between the fuel assembly components into which the converter is to be inserted is about 2 mm. In this regard, the search device consists of a transducer supported by a carrier which can pass through a limited space. The converter is arranged side by side with the plenum at the bottom of the fuel cell under test. It is known that ultrasound waves with a frequency of 5-15 MHz are easily propagated through water. In contrast, at frequencies in the megahertz range, ultrasonic attenuation is high in air or other gases. At frequencies corresponding to a few megahertz, ultrasonic pulses are introduced across the walls of the nuclear fuel body. If the fuel body is not incomplete, only the gas will be in the lower plenum and the high reflection coefficient at the complete metal-gas interface will impede the propagation of the pulse across the inner surface of the cladding.

In contrast, if the fuel body is incomplete and the underlying plenum contains water, the reflection coefficient of the metal-liquid boundary at the inner surface of the coating will be lower than that calculated at the metal-gas boundary. Thus, an important part of the pulse will propagate through the water to the opposite wall, reflect and return to the transducer. When reflections are detected from the opposite wall, it indicates water seeps into the fuel cell. Various new features that characterize the invention have been described in detail in the specification and claims. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS In order to better understand the operational superiority of the apparatus according to the present invention, and the specific objects achieved by using such apparatus, the accompanying drawings and illustrated embodiments will be described in detail as follows.

1 shows an ultrasound search apparatus 20. The search device 20 comprises an ultrasonic transducer 21 and a strip carrier 22, the strip carrier 22 having the opposing faces 23 and 24 and the transducer 21 suitably as shown in FIG. It has a hole to be inserted. The transducer 21 is a polarized ferroelectric ceramic having electrodeposited or discharged electrodes on two surfaces of the transducer, arranged in a hole such that one side 25 of the transducer is flush with the side 23 of the strip carrier 22. The opposite side of the transducer is placed in the hole and abuts the acoustic damping material 26. A decoupling insulation 30 is located between the perimeter of the hole and each of the opposing faces of the transducer 21. The transducer 21 is held firmly in the hole by an electrically nonconductive binder 31. The face 25 of the transducer 21, which is flush with the face 23 of the strip carrier, is grounded to the carrier. Grounding is accomplished by multiple spot welding conductors 32 or other suitable means.

Decoupling insulation 30 is disposed therebetween to minimize ultrasonic coupling between the transducer and the carrier. The coaxial cable 33 has an inner conductor 34 and an outer conductor 35 and is attached to the end portion 36 of the strip carrier. The inner conductor 34 is attached to the transducer 21, and the outer conductor 35 is attached to the strip carrier 22.

The search device 20 should be able to move freely in a limited gap of 2 mm between the fuel assembly and the control element injectors densely arranged in the fuel assembly. Therefore, the search device 20 and the separate components of the search device must be selected to meet certain dimensional requirements without compromising the ultrasonic properties required to apply the principles of detection technology.

The search device devised by the principles of the present invention comprises a transducer manufactured from lead zirconate or lead titanate, 2.5 mm wide, 12.5 mm long, 0.3 mm thick and mounted in an aluminum carrier. The transducer is insulated from the perimeter of the hole by a cork layer. The front and back sides of the transducer are clad with discharged silver electrodes and the same height as one side of the carrier is grounded to adjacent aluminum at several points through a copper wire tack welded to both aluminum and silver electrodes. . In order to smooth the surface into the fuel assembly, the surface of the converter and the entire copper wire may be covered with a conductive epoxy resin layer on the surface of the carrier. The damper 26 consists of two layers of tungsten powder mixed with low molecular weight polysulfide polymer.

Special dampeners include tungsten powder with an average particle size of 1.33 microns and an average particle size of 4.5 microns, manufactured by Tiocol Chemical Corporation of Trenton, New Jersey, and mixed with a low molecular weight polysulfide polymer called thiocol LP-3. There is a mixture of phosphorus tungsten powder. Non-conductive epoxy resins are used to harden the transducers in the holes. The surface of the ceramic recessed in the hole is connected to the inner conductor of the coaxial cable arranged along the end of the carrier. Other arrangements, frames, or materials can be used in the transducer as long as the search device can be inserted between the parts of the fuel assembly. In another embodiment, for example, a hollow tubular carrier comprising a coaxial cable was used. 3 is a plan view of the navigation device 20 arranged side by side in the plenum at the bottom of the nuclear fuel assembly 40 as a cutting portion of the fuel assembly. In order to transmit ultrasonic energy into the nuclear fuel body, a transducer connected to the nuclear fuel body 40 is energized by a vibrator (not shown) that emits pulses at a predetermined speed and frequency.

The sweep of the oscilloscope is synchronized to represent the transmitted and reflected pulses. The reflected wave is received by the scope through the transducer. If the fuel cell had not failed, the gas would be the only fluid present in the lower plenum and the high coefficient of reflection at the metal-gas interface would impede the propagation of the ultrasonic waves through the inner surface of the cladding. The reactions shown on a conventional pulse echo over a gas-filled nuclear fuel cell are shown in the oscillogram of Figure 4, with the time axis t being given. Expresses the resulting representation at the frequencies of oscillograms 7 megahertz in FIGS. 4, 6, and 7, with a distance of about 3 microseconds on the t-axis and an outer diameter of the fuel body of less than 0.5 inches.

In FIG. 4, the transmitted signal is substantially mixed with the reception code reflected from the first or front boundary of the gas-metal due to the low transmission coefficient of the gas. In contrast, if the fuel body fails and the underlying plenum contains water, the reflection coefficient on the landmark surface will be greatly reduced. Thus, an important portion of the ultrasonic pulse shown schematically in FIG. 5 will propagate through the liquid and will be reflected at the liquid-metal back interface in the fuel body 40. Therefore, a reflected signal of relatively distinct magnitude separated from the transmitted signal appears on the t-axis. The reactions shown on a conventional pulsed echocarder for incomplete, water-filled nuclear fuel bodies are shown in the oscillogram of FIG. An important response, seen at about 15 microseconds on the abscissa, indicates the echo received from the back wall.

The plenum underneath the nuclear fuel body generally has a threaded spring portion that may limit the free passage of the ultrasonic waves. But this does not represent an insurmountable difficulty. If the width of the piezoelectric body measured along the longitudinal axis of the nuclear fuel body is larger than the pitch of the thread springs, the sound waves will propagate back to the far wall. 7 shows a typical reaction of a nuclear fuel body filled with water with a spring. A typical ultrasonic apparatus has a gate circuit that generates a signal for a time interval selected with respect to the initial pulse. In addition, this circuit can be equipped to generate an alarm signal only when the ultrasonic signal amplitude exceeds a preset threshold level during the gate period.

If the gate is set to pass a signal between 12-15 microseconds on the axis, and a dressing hole of amplitude is placed on one line on the longitudinal axis, the presence of water, with or without springs, will be detected in the fuel cell. Can be. In operation, the search device is inserted between adjacent parts of the fuel assembly. Irradiated fuel assemblies are generally kept under water for cooling and shielding purposes during their transport in a reactor and are initially stored in spent fuel pools. Therefore, it is understood that the inspection of the nuclear fuel body is effective under water. The transducers are arranged side by side transverse to the longitudinal axis of the nuclear fuel body being tested. The pulses are then emitted in the fuel body at the converter. The fuel assembly can be tested by inserting a searcher into the fuel bundle without disassembling any parts of the fuel assembly. Therefore, fuel assemblies are moved out of the reactor only when inspected.

The technique can be extended to take advantage of multiplexed transducers that automatically and quickly test fuel assemblies in a fuel assembly.

Claims (1)

As shown and described in detail herein, in the apparatus used to test the fuel cell 40 to detect whether water is present inside the fuel cell 40 arranged at regular intervals in the fuel assembly for the water-cooled reactor, Electrodeposited on at least two surfaces of the strip carrier 22, the ultrasonic transducer 21, and the ultrasonic transducer 21, each having a hole facing the surfaces 23 and 24 and formed to be freely movable in the space between the nuclear fuel bodies. The ultrasonic transducer 21 formed of the electrode or the like and covered with the electrode 25 is mounted in the hole so as to have the same height as the one surface 2 of the strip carrier 22, and using the appropriate grounding means 32, the ultrasonic transducer (21) is grounded to the strip carrier 22, and the ultrasonic transducer 21 is decoupled from the strip carrier 22 as the decoupling insulating material 30 so that the decoupling insulating material 30 is formed around the hole. Inserted between the sonic transducers 21, the damping material 31 is placed in the hole adjacent to the portion in which the ultrasonic transducer 21 is placed, and the ultrasonic transducer 21 is energized with a coaxial cable 33 to test the chain under test. A device for detecting an incomplete nuclear fuel body adapted to transmit an ultrasonic pulse across a wall of the nuclear fuel body.

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