JP2001141875A - Shipping device - Google Patents

Abstract

PROBLEM TO BE SOLVED: To rapidly and easily specify a fuel assembly directly leaking at a field and to reduce exposure to a worker. SOLUTION: This shipping device is provided with a shipper cap 3, that is arranged at the upper portion of a reactor pressure container 4 and samples reactor water from a fuel assembly 1, a gas-liquid separation device 5 for extracting a radiation gas, while the reactor water being sampled by the shipper cap 3 is introduced, a measurement chamber 7 where the radiation gas being extracted by the gas-liquid separation device 5 is guided, and radiation- monitoring devices 8 and 9 for measuring the radiation gas guided to the measurement chamber 7 and obtaining the count rate.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a shipping apparatus for specifying a radioactive fuel assembly to be carried out after shutting down a reactor, when radioactive leakage occurs in a fuel assembly of a boiling water reactor. About.

[0002]

2. Description of the Related Art In a boiling water reactor, when radioactivity leaks into a fuel assembly, it is necessary to immediately identify the fuel assembly that has leaked radioactivity and replace it with a new fuel assembly. There is.

At present, in-core shipping for identifying this leaked fuel assembly is performed in the following procedure.

(1) A shipper cap is attached to a refueling machine and put on an upper tie plate of a fuel assembly to be inspected.

(2) Reactor water is guided to the sampling line via a pipe attached to the shipper cap due to residual decay heat of the fuel itself.

(3) Reactor water is pumped into a polyethylene container, taken back to the chemical analysis room, and after removing cladding and cations, radioactive iodine is adsorbed on an anion resin column or anion paper to detect Ge. Measure with a container. When radioactive iodine is detected in this measurement, it is determined that radioactivity is leaking into the fuel assembly.

[0007] The above is the in-core shipping. Another known technique is to load a fuel assembly in a closed container and measure beta rays from ⁸⁵ Kr emitted from the fuel assembly. In some cases, a means of shipping is also performed.

[0008]

Among such prior arts, in the in-core shipping, in order to perform a radioactive leakage inspection of an integrated fuel assembly, there are several steps of sampling, scientific pretreatment, and measurement. You have to take steps.

On the other hand, since the shipping inspection is performed on all of the huge number of fuel assemblies, there is a problem that the measurement cannot keep up with the frequency of sampling. In addition, since radioactive iodine is targeted for the determination of leakage, it may not be released into the reactor water depending on the size and position of the minute holes (pinholes) illuminated in the fuel assembly.

The present invention has been made in view of the above-described circumstances, and is capable of quickly and directly leaking a fuel assembly at a site.
It is another object of the present invention to provide a shipping device that can be easily specified and that can reduce the exposure of an operator.

[0011]

According to the present invention, in order to achieve the above object, a shipping apparatus is constituted by the following means.

[0012] The invention corresponding to claim 1 is provided above the open reactor pressure vessel, means for collecting the reactor water from the fuel assembly, and introducing the reactor water collected by the means. Means for extracting the radioactive gas in the reactor water, means for guiding the radioactive gas extracted by the extraction means to a measuring system, and a radiation monitor for measuring the radioactive gas guided to the measuring system and obtaining the counting rate Device.

In the shipping apparatus according to the first aspect of the present invention, a radioactive gas can be directly measured without performing many procedures such as sampling, pretreatment, and measurement of reactor water.

According to a second aspect of the present invention, there is provided a means for collecting reactor water from a fuel assembly, which is disposed above an open reactor pressure vessel, and introducing the reactor water collected by the means. Means for extracting radioactive gas from the reactor water, means for guiding the radioactive gas extracted by the extraction means to a measurement system, and counting rate of gamma rays from radionuclides contained in the radioactive gas guided to the measurement system Or a means for measuring the concentration and monitoring the concentration, whereby the position of the fuel assembly including the damaged fuel rod in the reactor is specified by the monitoring means.

In the shipping apparatus according to the second aspect of the present invention, the same operation and effect as those of the first aspect of the present invention can be obtained, and the counting rate of gamma rays from radionuclides contained in the radioactive gas or Since the concentration is measured,
The detection unit does not need to be exposed to the radioactive gas, and decontamination of the detection unit is unnecessary.

According to a third aspect of the present invention, in the shipping apparatus of the second aspect, the monitoring means is a wave height analyzer for energy discriminating gamma rays having a specific energy, and the energy is discriminated by the wave height analyzer. And a measurement processing means for continuously measuring the count rate or concentration of the gamma rays without missing measurement, and the wave height analyzer includes two or more or two or more storage units, one of which is used for wave height analysis. While the device or the storage unit is collecting data, the data subjected to energy discrimination by the other wave height analyzer or the energy discrimination data stored in the storage unit is transferred to the measurement processing means.

The invention according to claim 3 eliminates the need to control the start and stop of measurement every time the reactor water sampling means is moved to a position corresponding to each fuel assembly.

According to a fourth aspect of the present invention, in the shipping apparatus according to the second aspect, the monitoring means includes radioactive nuclides released from the damaged fuel rod into the reactor water, such as ⁸⁵ Kr and ¹³³ Xe. The position of the fuel assembly including the damaged fuel rod in the nuclear reactor is identified from the distribution of the radioactive rare gas.

In the shipping apparatus according to the fourth aspect of the present invention, among the radioactive rare gases released from the leaked fuel, ⁸⁵ Kr and ¹³³ Xe having a relatively long half life are monitored. Can be measured independently by energy discrimination.

According to a fifth aspect of the present invention, in the shipping apparatus according to the second aspect, the monitoring means monitors a count rate of all gamma rays of radionuclides released from the leaked fuel.

In the shipping apparatus according to the fifth aspect of the invention, since all gamma rays generated from the leaked fuel are measured, the detection sensitivity can be improved and the measurement system can be simplified.

According to a sixth aspect of the present invention, in the shipping apparatus of the second aspect, the monitoring means discriminates gamma rays of radionuclides emitted from the leaked fuel assembly from gamma rays of other radionuclides. It is provided with a Ge semiconductor detector such as a liquid nitrogen evaporation prevention type or a room temperature semiconductor detector such as CdZnTe which has a performance that can be performed.

In the shipping apparatus according to the present invention, maintenance work associated with replenishment of liquid nitrogen can be eliminated, and accordingly, exposure of workers is eliminated.

According to a seventh aspect of the present invention, in the shipping apparatus according to the first or second aspect, the means for extracting the radioactive gas in the reactor water collected by the collecting means includes the step of extracting the reactor water. It is constituted by a gas-liquid separation device which once jets into a space to separate a gas phase component and guides it to a measurement system.

In the shipping apparatus according to the present invention, the contaminated portion of the discharge system can be reduced.

According to an eighth aspect of the present invention, there is provided the shipping apparatus according to the seventh aspect, wherein a pure water replenishing water system is provided in a return pipe section for returning a liquid phase separated by the gas-liquid separation device to the reactor pressure vessel. Alternatively, a means for combining pure water or air from an air system is provided.

In the shipping apparatus according to the present invention, since the flow rate of the reactor water is increased and the agitation of the liquid phase is promoted, the discharge amount of the radioactive rare gas into the air is increased. Can be.

According to a ninth aspect of the present invention, in the shipping apparatus according to the first or second aspect, as means for collecting reactor water from the fuel assemblies, a plurality of fuel assemblies are provided. And a valve provided on a pipe for introducing the reactor water collected from these shipper caps to the radioactive gas extraction means, and a valve for opening and closing these valves. And a reactor water sampling control device for sequentially switching and selecting the reactor water sampled by each of the sipper caps to the extraction means and controlling the introduction thereof.

In the shipping apparatus according to the ninth aspect of the present invention, the reactor water introduced simultaneously from the plurality of fuel assemblies is selected by operating the valve and sequentially guided to the extracting means, so that the shipping is efficiently performed. An inspection can be performed.

According to a tenth aspect of the present invention, there is provided a reactor pressure vessel at an upper portion of an open reactor pressure vessel so as to correspond to a fuel assembly so that an air layer is formed above a reactor water level, and a side face of the reactor pressure vessel is provided. A sipper cap provided with a water discharge port, a stirrer provided on the sipper cap, and a stirrer for stirring a liquid phase portion in the sipper cap to extract a radioactive gas into an upper air layer; Means are provided for guiding the gas from the shipper cap to the measurement system, and a radiation monitoring device that measures the radioactive gas guided to the measurement system and obtains the counting rate.

[0031] The invention corresponding to claim 11 is provided corresponding to the fuel assembly such that an air layer is formed above the water surface of the reactor above the open reactor pressure vessel, and the side wall of the reactor is provided. A sipper cap provided with a water discharge port, a stirrer provided on the sipper cap, and a stirrer for stirring a liquid phase portion in the sipper cap to extract a radioactive gas into an upper air layer; Means for introducing gas from the shipper cap to the measurement system, and measuring the count rate or concentration of gamma rays from radionuclides contained in the radioactive gas guided to the measurement system to measure the fuel assembly including damaged fuel rods in the reactor And a monitoring means for specifying the position at the location.

In the shipping apparatus according to the tenth and eleventh aspects of the present invention, the gas-liquid separating apparatus can be simplified, and the equipment related to the discharge system can be omitted, as in the first and second aspects. The operation and effect of the present invention can be obtained.

[0033]

Embodiments of the present invention will be described below with reference to the drawings.

FIG. 1 is a schematic diagram showing the configuration of a first embodiment of a shipping apparatus according to the present invention.

In FIG. 1, reference numeral 1 denotes a plurality of fuel assemblies (only one fuel assembly is shown in FIG. 1) stored in a reactor pressure vessel 4 in a boiling water reactor. The assembly 1 contains a plurality of fuel rods inside.

Reference numeral 3 denotes a sipper cap which is placed on the upper tie plate 2 so as to cover the upper part of the fuel assembly 1 with the upper lid of the reactor pressure vessel 4 opened with respect to the fuel assembly 1. is there.

On the other hand, reference numeral 5 denotes a gas-liquid separator for introducing reactor water in the shipper cap 3 heated in the fuel assembly 1 through a pipe, and separates the reactor water into a gas phase and a liquid phase. A gas phase component disposed in the body 6 and separated by the gas-liquid separation device 5 is a measurement chamber through which a gas phase is guided. The liquid phase component retained in the measurement chamber 7 is separated in the gas-liquid separation device 5. The liquid phase is returned to the reactor pressure vessel through the return pipe together with the liquid phase.

Reference numeral 8 denotes a radiation monitor provided at an opening provided in a part of the collimator and the shield 6 so that a radiation incident portion faces the measurement chamber 7, and 9 denotes a radiation monitor in the measurement chamber 7 by the radiation monitor 8. A counting device 10 for receiving a gas measurement signal and measuring the counting rate is a display or recorder for displaying or recording the coefficient rate measured by the counting device 9.

Next, the operation of the shipping apparatus thus configured will be described.

Now, with the shipper cap 3 being put on the upper tie plate 2 as shown, the reactor water in the reactor in the fuel assembly 1 is heated by the residual decay heat of the fuel rods. If so, this reactor water is guided from the shipper cap 3 to the gas-liquid separator 5 through a pipe. In the gas-liquid separation device 5, the reactor water is discharged in a droplet form from the upper part, the liquid phase component accumulates in the lower portion, and the gas phase component is supplied from a pipe connected to the side of the gas-liquid separation device 5 through the measurement chamber 7. It is led to.

The radioactive gas in the measuring chamber 7 is
It is measured by the radiation monitor 8, and when the measurement signal is input to the counter 9, the counting rate is measured, and the operator is notified by a display or a recorder 10.

The liquid phase retained in the lower portion of the gas-liquid separator 5 is discharged through a pipe. At this time, the radioactive component retained in the measuring chamber 7 is operated according to the same principle as a suction device (aspirator) known in the chemical field. The gas is sucked, and the liquid phase is merged with the liquid phase discharged from the gas-liquid separator 5 and returned to the reactor pressure vessel through the return pipe.

As described above, in the first embodiment, when there is a leak in the fuel assembly 1, a gaseous phase component containing a radioactive gas stays in the measurement chamber 7, and this is transmitted to the radiation monitor 8.
The leaked fuel assembly can be identified by measuring the counting rate by the counting device 9 and measuring the radioactivity at the sampling site, which has been performed in many steps as in the prior art. Direct measurement can be performed, and labor can be saved and exposure of workers can be reduced.

FIG. 2 shows a second embodiment of the shipping apparatus according to the present invention.
2 is a schematic diagram showing the configuration of the embodiment, wherein the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description thereof will be omitted. Here, different points will be described.

In the first embodiment described above, among the radionuclides released from the leaked fuel, the beta-emitting nuclides have a detection unit of the radiation monitor 8 in consideration of the range and shielding effect of the measurement chamber 7. Must be exposed in the gas phase containing the radioactive gas. For this reason, every time a leaked fuel is found, the detection unit must be decontaminated, which lowers the work efficiency.

In order to prevent this, in the second embodiment, measurement is performed with the following configuration focusing on gamma rays among radioactive gases.

As shown in FIG. 2, a gamma ray detector 11 is provided in an opening of the collimator and the shield 6, and a detection signal of a gamma ray present in the radioactive gas detected by the gamma ray detector 11 is transmitted to a wave height analyzer 12. , And performs wave height analysis (energy discrimination), fetches the data into a data processing device 13 to calculate a gamma ray counting rate or radioactive concentration, and outputs the calculation result to a display, a recorder, or a printer 14. Things.

With the shipping apparatus having such a configuration, the same operation and effect as those of the first embodiment can be obtained. Of course, by using a gamma ray detector, the shipping apparatus can be used in a gas phase containing a radioactive gas. It is not necessary to expose, and it is not necessary to decontaminate the detecting unit every time a leaked fuel is found, so that the working efficiency can be improved.

Here, in the second embodiment,
Two or more memory units are built in the wave height analyzer 12, and while collecting measurement data in one memory unit, the measured data stored in the other memory unit is taken into the data processing unit 13 to count gamma rays. By repeating a series of processes of calculating the rate or the radioactivity concentration and outputting the result to a display, a recorder, or the printing device 14, data can be collected seamlessly and continuously, and efficient. It is.

Further, instead of having two memory units built in the wave height analyzer 12, two or more wave height analyzers are used, and while one of the wave height analyzers is collecting measurement data, the other wave height analyzer is used. The gamma ray measurement may be performed, and the measured data may be transferred to the data processing device 13.

Further, by measuring a radioactive rare gas such as ⁸⁵ Kr or ¹³³ Xe as a gamma ray emitting nuclide to be noted, it can be confirmed that the nuclide is emitted from the damaged fuel.

Here, a schematic diagram of the measured spectrum obtained from the wave height analyzer 12 is shown in FIG. That is, in the wave height analyzer 12, from the measurement spectrum 15 shown in FIG.
The net count 16 of a specific radioactive rare gas such as ⁸⁵ Kr or ¹³³ Xe is calculated, and the net count rate and radioactivity concentration of the specific nuclide of interest can be obtained therefrom.

When measuring the above-mentioned radioactive rare gas, when the concentration of the radioactive rare gas is low, all the count values of the measurement spectrum 15 are integrated to improve the detection sensitivity, and the count rate of all the gamma rays is monitored. You may make it.

In the above-described second embodiment of the present invention,
A gamma ray detector that detects gamma rays among radionuclides was used. This gamma ray detector has a good energy resolution and does not require maintenance during shipping inspection, such as a liquid nitrogen evaporation prevention type Ge semiconductor detector or CdZnTe. A room temperature semiconductor detector may be used.

FIG. 4 is a block diagram showing an embodiment in which a liquid nitrogen evaporation prevention type Ge detector is used.

As shown in FIG. 14, the Ge semiconductor detector 17
Is connected to a heat conductor inserted in a closed heat-insulating container 18 filled with liquid nitrogen so as to be coolable.
A refrigerator head 19 is attached to 8, and a compressor 20 that supplies gas to the refrigerator head 19 is connected.

The liquid nitrogen evaporation preventing type Ge having such a structure
If a detector is used, adiabatic expansion of the gas supplied from the compressor 20 to the heat insulating container 18 via the refrigerator head 19 causes
The inside of the heat insulating container 18 can be maintained at a temperature not higher than the liquefaction temperature of nitrogen, so that the liquid nitrogen can be used for a long time without evaporating the liquid nitrogen.

By providing the liquid nitrogen evaporation prevention type Ge detector 17 at the opening of the collimator and the shield shown in FIG. 2, the work of replenishing liquid nitrogen can be omitted in the shipping inspection, and an efficient measuring operation can be performed. Can be performed.

FIG. 5 shows a third embodiment of the shipping apparatus according to the present invention.
It is a schematic diagram which shows the structure of 1st Embodiment.

In FIG. 1 or FIG.
Is dependent on the residual decay heat of the fuel assembly 1. Therefore, the flow rate changes depending on the fuel assembly to be inspected, and the amount of radioactivity per unit time also changes.

In the third embodiment, in order to optimize this point, as shown in FIG. 5, the return pipe section of the gas-liquid separator 5 is provided with a pure water makeup water system (MUWP) or an in-house air system (SA).
By mixing pure water or air from 21 and adjusting the flow rate, the flow rate of the reactor water from the shipper cap can be made constant, and the amount of transfer of the radioactive gas to the gas phase can be increased.

FIG. 6 shows a fourth embodiment of the shipping apparatus according to the present invention.
It is a schematic diagram which shows the structure of 1st Embodiment.

In the fourth embodiment, instead of providing a pure water makeup water system (MUWP) or an in-house air system (SA) in the return pipe of the gas-liquid separator 5, a pump is provided in the return pipe as shown in FIG. 22.

With such a configuration, the gas-liquid separation device 5
The flow rate of the reactor water passing through can be stabilized.

FIG. 7 shows a fifth embodiment of the shipping apparatus according to the present invention.
It is a schematic diagram which shows the structure of 1st Embodiment.

As shown in FIG. 7, the shipper cap 23 is placed on the tie plate 2 located at a position corresponding to the upper part of the fuel assembly 1. The shipper cap 23 has a reactor water discharge port 24a on a side surface and a gas outlet 24b on the upper surface for connecting a radioactive gas to a gas-liquid separator (not shown), and is mounted on the tie plate 2. An air layer 25 is formed in the shipper cap 23 above the reactor water level.

Further, the shipper cap 2 is provided on the side of the shipper cap 23 opposite to the reactor water discharge port 24a.
A stirrer 26 for stirring the reactor water in 3 is attached.

In the shipping apparatus having such a configuration, when the reactor water pushed up by the residual decay heat of the fuel assembly 1 flows into the shipper cap 23, the reactor water is stirred in the shipper cap 23 by the stirring device 26. The mixture is stirred, and the gas phase is transferred to the upper air layer 25. At this time, the liquid phase component is discharged from the reactor water discharge port 24.

Then, only the radioactive gas transferred to the upper air layer 25 is led to the measurement system.

Therefore, with such a configuration, the gas-liquid separator of the measuring system can be simplified, and the equipment related to the discharging system can be omitted.

FIG. 8 shows a sixth embodiment of the shipping apparatus according to the present invention.
It is a schematic diagram which shows the structure of 1st Embodiment.

In the sixth embodiment, the pure makeup water system 27 is connected to the upper part of the gas-liquid separation device 5 and the air system 28 for flowing air into the measurement chamber 7 is connected.

With this configuration, after a leaked fuel assembly is found, radioactive substances remain in the gas-liquid separator 5 and the measurement chamber 7, but pure water is supplied from the pure makeup water system 27 and the air system 28 respectively. The radioactive material can be removed by flowing air and air.

Although not shown, it goes without saying that valves and check valves are provided in the system.

FIG. 9 shows a seventh embodiment of the shipping apparatus according to the present invention.
2 is a schematic diagram showing the configuration of the embodiment, and the same parts as those in FIG. 1 are denoted by the same reference numerals and the description thereof will be omitted, and only different points will be described here.

In the seventh embodiment, as shown in FIG. 9, the shipper caps 29 are placed on the tie plate 2 so as to correspond to the plurality of fuel assemblies 1, respectively, and communicate with the insides of the respective shipper caps 29. The pipes connected to the gas-liquid separator 5 are connected in common, and valves 32 are provided for each pipe, and these valves 32 are switched by the reactor water sampling control device 30. It was done.

With such a configuration, the reactor water guided to the gas-liquid separator 5 from the sipper caps 29 corresponding to the plurality of fuel assemblies 1 is switched by the reactor water sampling control device 30 to the valve. It is selected by 32 and guided to the gas-liquid separation device 5. In this case, the reactor water sampling control device 30 operates in conjunction with the measurement system.

As a result, the shipping inspection can be performed efficiently.

[0079]

As described above, according to the shipping apparatus of the present invention, the radionuclide from the leaked fuel assembly is
Since direct measurement and monitoring can be performed, and a radioactive rare gas as a target nuclide can be measured separately from the liquid phase, a leaked fuel assembly can be specified more reliably than in the past. Further, since many procedures such as sampling, pretreatment, and measurement are not performed as in the related art, efficient shipping can be performed. Furthermore, since there is no need for artificial work such as sampling and pretreatment,
Exposure to workers can be reduced, and radioactive waste generated by pretreatment can be eliminated.

[Brief description of the drawings]

FIG. 1 is a schematic diagram showing a configuration of a first embodiment of a shipping apparatus according to the present invention.

FIG. 2 is a schematic diagram showing a configuration of a second embodiment of a shipping device according to the present invention.

FIG. 3 is a diagram showing a measurement spectrum obtained from a pulse height analyzer in the embodiment.

FIG. 4 shows a liquid nitrogen evaporation preventing type G in the embodiment.
The block diagram in the case of using an e detector.

FIG. 5 is a schematic diagram showing a configuration of a radioactive gas extraction unit in a third embodiment of the shipping apparatus according to the present invention.

FIG. 6 is a schematic diagram showing a configuration of a radioactive gas extraction unit in a fourth embodiment of the shipping apparatus according to the present invention.

FIG. 7 is a schematic diagram showing a configuration of a reactor water sampling unit in a fifth embodiment of the shipping apparatus according to the present invention.

FIG. 8 is a schematic diagram showing the configuration of a radioactive gas extraction unit in a sixth embodiment of the shipping apparatus according to the present invention.

FIG. 9 is a schematic diagram showing a configuration of a sixth embodiment of the shipping apparatus according to the present invention.

[Explanation of symbols]

 DESCRIPTION OF SYMBOLS 1 ... Fuel assembly 2 ... Tie plate 3 ... Shipper cap 4 ... Reactor pressure vessel 5 ... Gas-liquid separation device 6 ... Collimator and shield 7 ... Measurement chamber 8 ... Radiation monitor 9 ... Counting device 10 Recorder 11 Gamma ray detector 12 Wave height analyzer 13 Data processing device 14 Printing device 17 Ge semiconductor detector 18 Insulated container 19 Refrigerator head 20 Compressor 21 Pure water make-up water system or air system 22 Pump 23 Shipper cap 24a Reactor water outlet 25 Gas layer 26 Stirrer 27 Pure make-up water system 28 Air system 29 ... Shipper cap 30 ... Reactor water sampling controller 31 ... Valve

[Procedure amendment]

[Submission date] July 28, 2000 (2007.2
8)

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[0012] The invention corresponding to claim 1 is provided at an upper part of an open reactor pressure vessel, and means for collecting reactor water from the fuel assembly, and temporarily collecting the reactor water collected by the means. A gas-liquid separation device that separates gaseous components by squirting into a space, means for guiding the radioactive gas separated by the gas-liquid separation device to a measurement system, and measuring the radioactive gas guided to the measurement system, A radiation monitoring device for determining the counting rate and a return pipe portion for returning the liquid phase separated by the gas-liquid separation device to the reactor pressure vessel are provided in the pipe portion. Means for joining air from the system.

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In the shipping apparatus according to the first aspect of the present invention, a radioactive gas can be directly measured without performing many procedures such as sampling, pretreatment, and measurement of reactor water. Further, the contaminated portion of the discharge system can be reduced.
Further, since the flow rate of the reactor water is increased to promote the liquid phase agitation, the amount of the radioactive rare gas released into the air can be increased.

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According to a second aspect of the present invention, there is provided a means disposed at an upper portion of an open reactor pressure vessel for collecting reactor water from a fuel assembly, and temporarily collecting the reactor water collected by the means. A gas-liquid separation device that separates a gaseous phase component by squirting it into a space, means for guiding a radioactive gas separated by the gas-liquid separation device to a measurement system, and a gas contained in the radioactive gas guided to the measurement system Data processing means for measuring the count rate or radioactivity concentration of gamma rays from radionuclides and outputting the result to a display, recorder or printing device; and the reactor for separating the liquid phase separated by the gas-liquid separator. A means is provided in the return pipe section for returning to the pressure vessel, and the pipe section has means for merging pure water from the pure water makeup water system or air from the air system.

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In the shipping apparatus according to the second aspect of the present invention, the same operation and effect as those of the first aspect of the present invention can be obtained, and the counting rate of gamma rays from radionuclides contained in the radioactive gas or Since the radioactive concentration is measured, it is not necessary to expose the detector to the radioactive gas,
No need to decontaminate the detector.

[Procedure amendment 6]

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According to a third aspect of the present invention, there is provided an upper part of an open reactor pressure vessel corresponding to a fuel assembly such that an air layer is formed above a reactor water level, and a side face of the reactor is provided. A sipper cap provided with a water discharge port, a stirrer provided on the sipper cap, and a stirrer for stirring a liquid phase portion in the sipper cap to extract a radioactive gas into an upper air layer; Means are provided for guiding the gas from the shipper cap to the measurement system, and a radiation monitoring device that measures the radioactive gas guided to the measurement system and obtains the counting rate.

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According to a fourth aspect of the present invention, there is provided an upper part of an open reactor pressure vessel in correspondence with a fuel assembly such that an air layer is formed above a reactor water level, and a side face of the reactor is provided. A sipper cap provided with a water discharge port, a stirrer provided on the sipper cap, and a stirrer for stirring a liquid phase portion in the sipper cap to extract a radioactive gas into an upper air layer; Means for introducing gas from the shipper cap to the measurement system, and measuring the counting rate or radioactivity concentration of gamma rays from radionuclides contained in the radioactive gas guided to this measurement system, and displaying the result on a display, recorder or printout Data processing means for outputting to the device.

[Procedure amendment 8]

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[Correction contents]

In the shipping apparatus according to the third and fourth aspects of the present invention, the gas-liquid separation apparatus can be simplified.
Claims 1 and 2 even if equipment related to the discharge system is omitted.
The same operation and effect as described above can be obtained.

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[Procedure amendment]

[Submission date] October 30, 2000 (2000.10.
30)

[Procedure amendment 1]

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As shown in FIG . 4 , the Ge semiconductor detector 17 is connected to a heat conductor inserted in a sealed insulated container 18 filled with liquid nitrogen so as to be coolable .
Is equipped with a refrigerator head 19, and the refrigerator head 1
9 is connected to a compressor 20 for supplying gas.

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Accordingly, with such a configuration , the gas-liquid separator of the measuring system can be simplified, and the equipment relating to the discharging system can be simplified.
It can be omitted.

[Procedure amendment 7]

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[Correction contents]

In the seventh embodiment, as shown in FIG. 9, the shipper caps 29 are placed on the tie plate 2 so as to correspond to the plurality of fuel assemblies 1, respectively, and communicate with the insides of the respective shipper caps 29. The piping connected to the gas-liquid separator 5 is connected in common, and valves 31 are provided for the respective pipings, and these valves 31 are switched by the reactor water sampling control device 30. It was done.

(72) Inventor Taichi Koyashiki 1 Toshiba-cho, Fuchu-shi, Tokyo Inside the Toshiba Fuchu Plant, Inc. (72) Inventor Mitsuru Oikawa 1-toshiba-cho, Fuchu-shi, Tokyo Inside the Fuchu Plant, Toshiba F-term ( Reference) 2G075 AA03 BA17 CA38 DA08 DA10 DA16 EA01 FA18 FC14 GA16 GA21 GA37

Claims (11)

[Claims] 1. A means for collecting reactor water from a fuel assembly disposed at an upper part of an open reactor pressure vessel, and a radioactive gas in the reactor water into which the reactor water collected by the means is introduced. And a means for guiding the radioactive gas extracted by the extraction means to a measuring system, and a radiation monitoring device for measuring the radioactive gas guided to the measuring system and obtaining the counting rate. Characteristic shipping equipment. 2. A means for collecting reactor water from a fuel assembly disposed at an upper part of an open reactor pressure vessel, and a radioactive gas in the reactor water into which the reactor water sampled is introduced. Extraction means, means for guiding the radioactive gas extracted by the extraction means to the measurement system, and measurement by measuring the count rate or concentration of gamma rays from radionuclides contained in the radioactive gas guided to the measurement system, causing damage. A shipping apparatus comprising: a monitoring unit that specifies a position of a fuel assembly including a fuel rod in a nuclear reactor. 3. A shipping apparatus according to claim 2, wherein said monitoring means includes a wave height analyzer for energy discriminating a gamma ray having a specific energy, and a count rate or a concentration of the gamma ray energy discriminated by said wave height analyzer. And a measurement processing means for performing a continuous measurement process in the wave height analyzer, comprising two or more or two or more storage units, while one of the wave height analyzer or storage unit is collecting data, A shipping apparatus characterized in that data discriminated by the other wave height analyzer or energy discriminated data stored in the storage unit is transferred to the measurement processing means. 4. A shipping apparatus according to claim 2, wherein the monitoring means monitors a radioactive rare gas such as ⁸⁵ Kr or ¹³³ Xe among radioactive nuclides released into the reactor water from the damaged fuel rod, and monitors the radioactive nuclide. A shipping apparatus characterized in that a position of a fuel assembly including a damaged fuel rod in a reactor is specified from a distribution of a rare gas. 5. The shipping apparatus according to claim 2, wherein the monitoring means monitors a count rate of all gamma rays of radionuclides released from the leaked fuel. 6. The shipping apparatus according to claim 2, wherein the monitoring means has a capability of discriminating gamma rays of radionuclides emitted from the leaked fuel assembly from gamma rays of other radionuclides and has an ability to discriminate energy with gamma rays of other radionuclides. Or a room-temperature semiconductor detector such as CdZnTe. 7. The shipping apparatus according to claim 1 or 2, wherein the means for extracting the radioactive gas in the reactor water collected by the sampling means is configured to once eject the reactor water into the space to remove the gaseous phase. Characterized by a gas-liquid separation device that separates the liquid and introduces it into a measurement system. 8. The shipping apparatus according to claim 7, wherein pure water or air is joined from a pure water makeup water system or an air system to a return pipe portion for returning a liquid phase separated by the gas-liquid separator to the reactor pressure vessel. A shipping device comprising means for causing the shipping device. 9. The shipping apparatus according to claim 1, wherein the means for collecting the reactor water from the fuel assemblies corresponds to each of the plurality of fuel assemblies and enables the reactor water to be sampled at the same time. The provided sipper caps, the valves provided on the pipes for introducing the reactor water collected from the sipper caps to the extraction means of the radioactive gas, and the valves were opened and closed to collect the sipper caps. A reactor water sampling control device for sequentially switching and selecting the reactor water to the extraction means and controlling the introduction thereof; 10. A shipper provided at an upper portion of an open reactor pressure vessel in correspondence with a fuel assembly so that an air layer is formed above a reactor water surface, and provided with a reactor water discharge port on a side surface. A cap, a stirrer provided on the sipper cap, agitating a liquid phase portion in the sipper cap to extract a radioactive gas to an upper air layer, and a measuring system for measuring the radioactive gas extracted by the stirrer from the sipper cap. , And a radiation monitoring device that measures a radioactive gas guided to the measurement system and obtains a counting rate of the radioactive gas. 11. A shipper provided at an upper portion of an open reactor pressure vessel in correspondence with a fuel assembly so that an air layer is formed above a reactor water surface, and provided with a reactor water discharge port on a side surface. A cap, a stirrer provided on the sipper cap, agitating a liquid phase portion in the sipper cap to extract a radioactive gas to an upper air layer, and a measuring system for measuring the radioactive gas extracted by the stirrer from the sipper cap. And a monitor for measuring the gamma ray counting rate or concentration from radionuclides contained in the radioactive gas guided to the measurement system to identify the position of the fuel assembly including the damaged fuel rod in the reactor. And a means for shipping.