JP2019113346A - Nuclear fuel nuclide categorization method and apparatus therefor - Google Patents

Abstract

To provide a nuclear fuel nuclide categorization method and apparatus.SOLUTION: As a matter of course, a nuclear fuel nuclide categorization method makes it possible to determine whether a measurement target contains a nuclear fuel, whether the measurement target contains a variety of α, whether the measurement target is treated as an α waste, whether the measurement target is treated as a general waste, whether the measurement target is treated as a nuclear fuel material, whether the measurement target is treated as fuel debris, and the method makes it possible to categorize the measurement target into fuel debris and waste, to categorize the measurement target into nuclear fuel and waste; to categorize the measurement target into a target nuclide for measurement management and the others; and to categorize the measurement target into a target nuclide for safeguard and the others and to evaluate them. The method makes it possible to evaluate whether the measurement target is a material for identification, measurement and removal of a specific nuclide, whether the measurement target is a material that does not cause a critical phenomenon even if removed, whether the measurement target is a material that causes the critical phenomenon when removed, and whether the measurement target contains a material for identification, measurement and removal of a specific nuclide. In addition, the method evaluates and determines initialization and completion of operations such as identification, measurement and removal of a specific nuclide of a material in order to identify, measure, and remove the specific nuclide.SELECTED DRAWING: Figure 1

Description

  The present invention relates to a method and apparatus for separating nuclear fuel nuclides, and is particularly suitable for evaluating / determining whether or not each operation of inspection, work, construction, sorting, and removal of an object to be measured by the concentration or concentration ratio of nuclear fuel nuclides Method and apparatus for the separation of nuclear fuel

  In general, nuclear power generation facilities that use nuclear fuel, dismantling facilities for nuclear power generation facilities, nuclear reactor decommissioning facilities, nuclear fuel manufacturing facilities, nuclear fuel handling facilities, nuclear fuel storage facilities, nuclear fuel reprocessing facilities, waste storage facilities, military Facilities, the above facilities which caused an accident, nuclear power facilities which caused an accident, dismantling and decommissioning facilities of accident furnaces, fuel debris retrieval facilities, fuel debris investigation facilities, fuel debris sorting facilities, fuel debris storage facilities, etc. General nuclear facilities focus on specific nuclides in the nuclear power facilities, dismantling facilities of nuclear power facilities, decommissioning facilities of nuclear reactors, waste storage facilities, etc. The technical field and specific of detecting, measuring and monitoring these nuclides It is necessary to conduct surveys, construction, separation and removal while detecting, measuring and monitoring nuclides in nuclides.

  Patent documents 1, 2, 3 and 4 can be mentioned as a prior art document which disclosed the analysis method which specifies the element of the measuring object things, such as such a radioactive substance.

  In Patent Document 1 described above, the peak ratio of emission intensity to a plurality of specific decomposition products in an arbitrary plasma-ized substance spectrum and the composition cost are derived by laser induced breakdown analysis and specified with reference to the substance identification ratio. It is described.

  Further, Patent Document 2 describes that a laser is irradiated to a measurement object by laser induced breakdown analysis, and the element and content of a substance to be analyzed are determined based on the intensity of a specific emission line. .

  Patent Document 3 also includes a plurality of sample cells irradiated with laser light, a first detector for detecting a pressure wave generated by the laser light irradiation, and a second detector for detecting plasmatized plasma light. , And a third detector for detecting fluorescence, which is described to analyze different elemental concentrations.

  Further, in Patent Document 4, a radioactive melt is pulverized by a pulse laser, supported on a filter to form a sample, and X-rays are irradiated to detect fluorescent X-rays generated to calculate an element concentration. Have been described.

JP, 2013-245989, A Japanese Patent Application Publication No. 2007-003510 Japanese Patent Laid-Open No. 2000-235001 JP, 2016-075601, A

  However, in Patent Documents 1, 2, 3 and 4 mentioned above, whether or not the object to be measured contains nuclear fuel, whether it contains α various types, whether it is treated as α waste, whether it is treated as general waste Whether or not it is handled as nuclear fuel material, whether it is handled as fuel debris, fuel debris and waste separation, nuclear fuel and waste separation, measurement control target nuclides and other classifications, safeguards target nuclides and others If it can not be separated and evaluated, or if it is a material for the purpose of identification, measurement and removal of specific nuclides, if it is a material that does not cause a critical phenomenon even if it is removed It can not be evaluated whether or not there is a material for which identification, measurement, and removal of a specific nuclide exist, whether or not the material causes a critical phenomenon. Furthermore, there is a problem that the start and completion of work such as identification, measurement and removal of a specific nuclide of a material for the purpose of identification, measurement and removal of a specific nuclide can not be evaluated or judged.

  The present invention has been made in view of the above-described point, and the purpose of the present invention is to determine whether the object to be measured contains nuclear fuel, whether it contains α various types, whether it is handled as α waste, general waste Whether to handle as nuclear waste, whether to handle as nuclear fuel material, whether to handle as fuel debris, separation of fuel debris and waste, separation of nuclear fuel and waste, separation of target nuclides of measurement management, other separation, safeguards Of course, it is possible to separate and evaluate target nuclides and other nuclides, and whether or not the target is a material for identification, measurement and removal of specific It can be evaluated whether it is a material, whether it is a material that causes a critical phenomenon if removed, whether there is a material for the purpose of identification, measurement and removal of a specific nuclide, and furthermore, identification, measurement and removal of a specific nuclide Core of the material for the purpose The present invention is to provide a method and apparatus for separating nuclear fuel nuclides capable of evaluating and judging the start and completion of work such as identification, measurement and removal work of species.

  In order to achieve the above object, the method for separating nuclear fuel nuclides of the present invention is a material for the purpose of identification, measurement and removal of specific nuclides scattered in facilities using nuclear fuel, general nuclear facilities or nuclear facilities where an accident occurred. Measuring the concentration or concentration ratio of the specific nuclide), and based on the measured concentration or concentration ratio of the material, to evaluate / determine whether or not each operation of survey, work, construction, sorting, and extraction in the facility It features.

  In addition, in order to achieve the above object, the apparatus for separating nuclear fuel nuclides according to the present invention aims to identify, measure and remove specific nuclides scattered in facilities using nuclear fuel, general nuclear facilities or nuclear facilities where an accident occurred. Measuring device for measuring concentration or concentration ratio of material (specific nuclide), gripping device for gripping the material, measuring device for measuring concentration or concentration ratio of the material gripped by the gripping device, or suction the material Suction device, a measuring device for measuring the concentration or concentration ratio of the material sucked by the suction device, a holding device for holding the measuring device or the material, and a concentration of the material held by the holding device Measured by a measuring device for measuring concentration ratio, or a suction device for sucking the material, and a measuring device for measuring concentration or concentration ratio of the material sucked by the suction device Based on the concentration of the material, research in the facility, work, work, separation, characterized in that it and a evaluation and determining evaluation device permission for the work of taking out.

  According to the present invention, whether or not the object to be measured contains nuclear fuel, whether it contains α various types, whether it is handled as α waste, whether it is handled as general waste, whether it is handled as nuclear fuel material And whether it will be handled as fuel debris, separation of fuel debris and waste, separation of nuclear fuel and waste, separation of radionuclides from measurement control nuclides and other separations, separation and assessment of safeguards from radionuclides and other separations Of course, whether or not the measurement object is a material for the purpose of identification, measurement and removal of a specific nuclide, whether it is a material that does not cause a critical phenomenon even if it is removed, or if it is a material that causes a critical phenomenon. It is possible to evaluate whether or not there is a material for identification, measurement and removal of a specific nuclide, and further to identify, measure and remove a specific nuclide of the material for identification, measurement and removal of a specific nuclide. Work start and work such as work Evaluate and judge completion.

BRIEF DESCRIPTION OF THE DRAWINGS It is a figure which shows the nuclear power generation plant used as the object of Example 1 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the measuring method which measures the nuclide employ | adopted in Example 1 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the modification of the measuring apparatus which measures nuclide as Example 2 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the modification of the measuring apparatus which measures nuclide as Example 3 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the modification of the measuring apparatus which measures nuclide as Example 4 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the modification of the measuring apparatus which measures nuclide as Example 5 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the modification of the measuring apparatus which measures nuclide as Example 6 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 7 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 8 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 9 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 10 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 11 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 12 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant which becomes object of Example 13 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation plant used as the object of Example 14 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the nuclear power generation facility used as the object of Example 15 of the separation method of nuclear fuel nuclide of this invention, and its apparatus. It is a figure which shows the flow in an identification, measurement, and evaluation apparatus of the specific nuclide as described in Example 1- Example 15 as Example 16 of this invention. It is a figure which shows the flow in an identification, measurement, and evaluation apparatus of the specific nuclide as described in Example 1- Example 15 as Example 17 of this invention. It is a figure which shows the flow of the Example in connection with the execution decision | availability of each operation | work of investigation, construction, classification | category, taking-out etc. as Example 18 of this invention as Example 18 of this invention. The figure which shows the flow of the Example regarding execution of execution of each work of investigation, construction, classification, taking-out etc., warning of warning issuing of warning, and issuance of evacuation as Example 19 of this invention. It is. As Example 20 of the present invention, the existence distribution of materials for the purpose of determining whether or not to carry out each work such as investigation, construction, separation, and removal described in Examples 1 to 19 and identification, measurement and removal of specific nuclide FIG. 6 is a diagram showing the flow of an embodiment involved in mapping and recording, storage and completion of each operation.

  Hereinafter, the method and apparatus for separating nuclear fuel nuclides according to the present invention will be described based on the illustrated embodiments. In each embodiment, the same reference numeral is used for the same component.

  Further, the specific nuclide to be described in the following examples refers to an nuclide U, Pu, Am, Np, etc. contained in nuclear fuel, a nuclear fuel nuclide U such as safeguarded object U, Pu etc, an nuclide Gd having an effect of suppressing critical phenomena, Radionuclides such as B, Hf, Sm, radionuclides Cs, Sr, I, Co, T, Eu, Tc, Ru, Ce, etc. present in facilities such as Si, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr , Mn, Mo, Nb, Ta, Ti and the like.

  FIG. 1 shows a nuclear power plant to be subjected to the first embodiment of the method for separating nuclear fuel nuclides according to the present invention and the apparatus thereof.

  In the present embodiment, a fuel debris retrieval facility, a decommissioning of an accident furnace, and a dismantling facility at a nuclear power generation facility which has caused an accident will be described as a representative example. In addition, a material for identification, measurement and removal of a specific nuclide is defined as a material for identification, measurement and removal of a specific nuclide.

  As shown in FIG. 1, the nuclear power facility includes a nuclear building 2, a containment vessel 3 (PCV: Primary Containment Vessel), a reactor pressure vessel 4 (RPV: Reactor Pressure Vessel), and a pedestal supporting the reactor pressure vessel 4. There are five.

  The present embodiment will be described as a representative example of the identification, measurement and removal of the material 1 a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5.

  The articulated arm 6 is inserted from the lateral outside of the containment vessel 3 of the nuclear power plant, and at the tip of the articulated arm 6, a measuring device 7 for measuring nuclide is installed. The articulated arm 6 is stored in the cell 8 and airtightness is maintained. Material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside pedestal 5 of nuclear power plant is identified by measurement device 7 for measuring nuclide provided at the tip of articulated arm 6, Measurement is performed, identification of specific nuclide, measurement and evaluation device (hereinafter simply referred to as evaluation device) 9 identification of nuclide (whether or not nuclide exists), measurement (how much nuclide exists) and evaluation (how much Whether to make corrections etc.) is implemented.

  Based on the evaluation result by the evaluation device 9, identification, measurement and removal of a specific nuclide of the material 1a for the purpose of identification, measurement and removal of a specific nuclide scattered inside the pedestal 5 are performed.

  By this evaluation, identification of specific nuclide scattered inside pedestal 5, identification and measurement of specific nuclide of material 1a for the purpose of removal, and measurement, identification of specific nuclide by the material, measurement and purpose of the material for the purpose of measurement and removal of specific nuclide And whether it is a material that does not cause a critical phenomenon even if it is removed, whether it is a material that causes a critical phenomenon if it is removed, and aims to identify, measure and remove specific nuclides scattered inside pedestal 5 Whether or not the material 1a is present can be evaluated.

  In this way, it is possible to evaluate and judge the start and completion of work such as identification, measurement and removal of a specific nuclide of the material 1 a for the purpose of identification, measurement and removal of a specific nuclide scattered inside the pedestal 5.

  That is, in the present embodiment, the concentration or concentration ratio of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 is measured, and the concentration or concentration ratio of the measured material 1a is measured. The evaluations and judgments of the investigation, work, construction, separation, and removal work at nuclear power facilities are made.

  Specifically, the concentration or concentration ratio of the material 1a for the purpose of identification, measurement and removal of the specific nuclide scattered inside the pedestal 5 measured by the measurement device 7 for measuring nuclide and the specific nuclide preset in advance A device (evaluation device 9) for comparing the concentration or concentration ratio target value of the material (specific nuclide) for identification, measurement and removal is provided, and the concentration or concentration ratio of the material 1a is preset in the device. The target value of the concentration or concentration ratio of the material is compared with the target value to evaluate / determine the propriety of the survey, work, construction, sorting, and extraction in the nuclear power plant.

  In Fig. 1 of this example, the fuel debris removal facility at the nuclear power facility that caused the accident, the decommissioning of the accident furnace, and the dismantling facility use nuclear fuel as the material for the purpose of identification, measurement and removal of specific nuclides. It corresponds to fuel debris that has melted or dropped. Nuclear fuel also melts at nuclear power generation facilities that have caused accidents at nuclear fuel facilities, nuclear power generation facility dismantling facilities, nuclear reactor decommissioning facilities, nuclear fuel manufacturing facilities, nuclear fuel handling facilities, nuclear fuel storage facilities, nuclear fuel reprocessing facilities Fuel debris and so on.

  Facilities using nuclear fuel include nuclear power generation facilities, dismantling facilities for nuclear power generation facilities, nuclear reactor decommissioning facilities, nuclear fuel manufacturing facilities, nuclear fuel handling facilities, nuclear fuel storage facilities, nuclear fuel reprocessing facilities, waste storage facilities, military facilities, The facilities mentioned above that caused the accident, the nuclear power generation facilities that caused the accident, the dismantling and decommissioning facilities of the accident furnace, the fuel debris retrieval facility, the fuel debris investigation facility, the fuel debris sorting facility, the fuel debris storage facility, etc. This embodiment can be applied.

  General nuclear facilities are nuclear power generation facilities, dismantling facilities for nuclear power generation facilities, decommissioning facilities for nuclear reactors, waste storage and the like, and this embodiment can be applied.

  In addition, the concentration ratio of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 is present in nuclear fuel nuclides and nuclides present in the facility, nuclides having the effect of suppressing the critical phenomenon and facilities Radionuclides, radionuclides, radionuclides present in facilities or nuclear fuel nuclides and nuclides having the effect of suppressing critical phenomena.

  Material 1a for identification, measurement and removal of specific nuclide scattered inside pedestal 5 mentioned above is a specific nuclide, nuclear fuel nuclide targeted for safeguards such as alpha nuclide U, Pu, Am, Np etc contained in nuclear fuel U, Pu, etc., nuclide Gd, B, Hf, Sm, etc., having a suppressing effect on critical phenomena, radionuclide Cs, Sr, I, Co, T, Eu, Tc, Ru, Ce, etc., nuclide Si present in facilities, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr, Mn, Mo, Nb, Ta, Ti and the like.

  In addition, alpha nuclides contained in nuclear fuel and nuclides present in facilities are Pu / Si, nuclear fuel nuclides targeted for the safeguards and nuclides present in facilities present Pu / Si, nuclides having the effect of suppressing the critical phenomenon and present in facilities The radionuclide is Gd / Si, the radionuclide and the nuclide present in the facility are Cs / Si, and the nuclear fuel nuclide and the nuclide having the effect of suppressing the critical phenomenon are Pu / Gd, and these nuclides and the specific nuclide are Nuclear nuclides U, Pu, Am, Np, etc. contained in nuclear fuel, nuclear fuel nuclides U, Pu, etc. subject to safeguards, nuclides Gd, B, Hf, Sm, etc., having effects of suppressing critical phenomena, radionuclide Cs, Sr, I etc. , Co, T, Eu, Tc, Ru, Ce, etc. Ratios of nuclide Si, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr, Mn, Mo, Nb, Ta, Ti etc. existing in the facility And their concentration ratio Is compared with a preset target value to evaluate / determine whether or not each operation of survey, work, construction, sorting, and extraction in the facility is possible.

  In addition, the concentration ratio of at least two or more nuclides of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 and the material for the purpose of identification, measurement and removal of preset specific nuclides An apparatus (evaluating apparatus 9) for comparing the target value of the concentration ratio of the specific nuclide) with the target value of the concentration ratio of the material 1a set beforehand by the apparatus In comparison, evaluate and judge the propriety of each work of investigation, work, construction, separation, and extraction in nuclear power generation facilities.

  At least two or more nuclides of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 described above are specific nuclides, α nuclide U, Pu, Am, Np, etc. contained in nuclear fuel, etc. Nuclear fuel nuclides U, Pu, etc. targeted by safeguards, nuclides Gd, B, Hf, Sm etc. with the effect of suppressing critical phenomena, radionuclides Cs, Sr, I, Co, T, Eu, Tc, Ru, Ce etc., facilities Of at least two or more of the nuclide such as Si, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr, Mn, Mo, Nb, Ta, Ti, etc. And the target value set in advance, to evaluate / determine the propriety of each work of survey, work, construction, sorting, and taking out at the nuclear power generation facility.

  In FIG. 1 of this embodiment, the material 1a is used for identification, measurement and removal of specific nuclides scattered inside the pedestal 5, but the position of the material for identification, measurement and removal of specific nuclides is Without being limited thereto, the same applies to the material 1 b for the purpose of identification, measurement and removal of specific nuclides scattered outside the pedestal 5.

  In the present embodiment, the atmosphere environment can be applied to a gas such as air or nitrogen, or to a liquid such as water.

  According to this embodiment, it is determined whether or not the object to be measured contains nuclear fuel, whether it contains α types, whether it is treated as α waste, whether it is treated as general waste, nuclear fuel material Whether to handle as fuel debris, whether it is handled as fuel debris, fuel debris and waste separation, nuclear fuel and waste separation, target nuclide and other classification of measurement control, safeguards target nuclide and other classification and evaluation Of course, it is possible to determine if the measurement object is a material for the purpose of identification, measurement and removal of a specific nuclide, whether it is a material that does not cause a critical phenomenon by It is possible to evaluate whether or not there is a material that produces, and whether there is a material for the purpose of identification, measurement and removal of a specific nuclide, and furthermore, for the specific nuclide of the material for the purpose of identification, Identification, measurement and removal Can evaluate and judge the start of work and work completion.

  Next, an example of the measuring apparatus 7 which measures the nuclide of the present Example mentioned above is shown.

  The measuring apparatus 7 for measuring nuclide shown in FIG. 2 comprises a laser transmitter 10 for generating laser light, a first optical fiber 11 for transmitting the laser light generated from the laser transmitter 10, and a first optical fiber 11 A condensing optical system 12 for condensing the transmitted laser light, and a material 1 a for the purpose of identification, measurement and removal of specific nuclide that scatters the laser light condensed by the condensing optical system 12 outside the pedestal 5 At this time, the component nuclide of the material 1a emitted from the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered in the pedestal 5 light (emission spectrum) 13 And a second optical fiber 15 for transmitting the light (emission spectrum) 13 collected by the collection optical system 14 to the evaluation device 9.

  That is, laser light is generated from the laser transmitter 10, and the laser light is transmitted using the first optical fiber 11 and condensed by the condensing optical system 12, and identification of specific nuclides scattered inside the pedestal 5; The material 1a intended for measurement and removal is irradiated. At this time, from the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 Light (emission spectrum) 13 originating from the constituent nuclide and element of

  The component nuclide and light (emission spectrum) 13 caused by the element are collected by the collection optical system 14 and transmitted using the second optical fiber 15, and the evaluation device 9 performs identification, measurement and evaluation of the specific nuclide Do.

  The component nuclide constituting the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, the element emits light (emission spectrum) 13 originating from the component nuclide or element, and this light It is possible to identify the nuclide from the wavelength, intensity or the like of (emission spectrum) 13.

  The laser beam and light (emission spectrum) 13 derived from the constituent nuclide and element can be transmitted to a long distance by the first optical fiber 11 and the second optical fiber 15, and the laser transmitter 10 and the evaluation device 9 are It can be installed at a long distance from the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5.

  For example, as shown in FIG. 1, the measuring device 7 for measuring nuclide is set in the reactor pressure vessel 4 having a high radiation dose, but the laser transmitter 10 and the evaluation device 9 have low radiation dose. It can be installed outside of 4. This can significantly reduce the damage to the device due to radiation.

  Further, laser light is generated from the laser transmitter 10, transmitted using the first optical fiber 11, and condensed by the condensing optical system 14 to identify, measure and remove specific nuclides scattered inside the pedestal 5. Examples of the method of irradiating the material 1a as the target and emitting light (emission spectrum) 13 caused by the constituent nuclide and element include a laser induced breakdown method and a laser induced fluorescence method.

  In addition, the laser transmitter 10 can also be used as a laser transmitter for cutting, dissolving, crushing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5. is there.

  Furthermore, the laser transmitter 10, a laser for cutting, dissolving, fracturing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 and a laser-induced breakdown method It is also possible to separately separately emit a laser and a laser for the purpose of laser induced fluorescence, and to perform irradiation in combination or common use.

  In addition, the laser transmitter 10, a laser for cutting, dissolving, fracturing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 and a laser-induced breakdown method By separately performing power modulation control and frequency modulation control separately and individually for the purpose of the laser and the laser induced fluorescence method, it is possible to perform irradiation by combining or sharing the output modulation control and frequency modulation control. It is possible to improve detection sensitivity and improve the signal-to-noise ratio (signal-to-noise ratio).

  In the present embodiment, the atmosphere environment can be applied to a gas such as air or nitrogen, or to a liquid such as water.

  FIG. 3 shows a modification of the measuring apparatus 7 for measuring the nuclide in FIG. 1 of the first embodiment as the second embodiment of the present invention.

  The measuring apparatus 7 for measuring nuclide shown in FIG. 3 comprises a laser transmitter 16 for generating laser light, an optical fiber 17 for transmitting the laser light generated from the laser transmitter 16, and a laser light transmitted by the optical fiber 17 A material 1a for the purpose of identification, measurement and removal of specific nuclides scattered in the pedestal 5 by the collection and collection optical system 18 for collection and collection and the laser light collected by the collection and collection optical system 18 To identify, measure and remove specific nuclides scattered inside pedestal 5, and identify, measure and remove specific nuclides scattered inside pedestal 5 emitted from the surface of material 1a Light (emission spectrum) 13 collected by the collection and collection optical system 18 and light (emission spectrum) 13 derived from the constituent nuclide and element of the target material 1a is collected by the collection and collection optical system 18 Optical fibers 17 and reverse transmission using, is schematically composed of a beam splitter 19 for transmitting to the evaluation apparatus 9 which branches the light (emission spectrum) came back.

  That is, laser light is generated from the laser transmitter 16, transmitted using the optical fiber 17, collected by the collection and collection optical system 18, identification, measurement and removal of specific nuclides scattered inside the pedestal 5 To the target material 1a. At this time, from the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 Emits light (emission spectrum) 13 attributed to the constituent nuclide and element.

  The light (emission spectrum) 13 derived from the constituent nuclide and the element is collected by the light collecting and collecting optical system 18, transmitted using the optical fiber 17, and returned (the light originating from the constituent nuclide and the element The spectrum 13) is branched using a beam splitter 19 such as a deflection plate, and the evaluation device 9 carries out identification, measurement and evaluation of specific nuclides.

  The component nuclide constituting the material 1a for the purpose of identification, measurement and removal of the specific nuclide interspersed inside the pedestal 5, the element emits a light (emission spectrum) 13 originating from the component nuclide and the element It is possible to identify the nuclide from the emission spectrum) 13 wavelength, intensity and the like.

  Laser light is generated from the laser transmitter 16, transmitted using the optical fiber 17, and collected by the collection optical system 18 for identification, measurement and removal of specific nuclides scattered inside the pedestal 5. The method of irradiating the material 1a to be made to emit light (emission spectrum) 13 derived from the constituent nuclide and element is a laser induced breakdown method or a laser induced fluorescence method.

  In addition, the laser transmitter 16 can also be used as a laser transmitter for cutting, dissolving, fracturing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5. is there.

  Furthermore, the laser transmitter 16 and a laser for cutting, dissolving, crushing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 and a laser-induced breakdown method are aimed for It is also possible to separately separately emit a laser and a laser for the purpose of laser induced fluorescence, and to perform irradiation in combination or common use.

  In the present embodiment, the atmosphere environment can be applied to a gas such as air or nitrogen, or to a liquid such as water.

  FIG. 4 shows a modification of the measuring apparatus 7 for measuring the nuclide in FIG. 1 of the first embodiment as the third embodiment of the present invention.

  The measuring apparatus 7 for measuring the nuclide shown in FIG. 4 is the same as that of the second embodiment shown in FIG. 3, but the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 is It is covered with a shatterproof cover 20 to prevent the diffusion of a product (hereinafter simply referred to as a product) 21 emitted from the surface upon laser irradiation. If necessary, the inside of the shatterproof cover 20 may be sucked to prevent the diffusion of the product 21.

  The shatterproof cover 20 is made of a hard material or a flexible material (e.g., rubber, sponge, etc.) that conforms to the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5.

  In addition, light (emission spectrum) 13 originating from the constituent nuclide and element is emitted from the constituent nuclide and element constituting the material 1a for the purpose of identification, measurement and removal of the specific nuclide scattered inside the pedestal 5. It is possible to identify the nuclide from the wavelength, intensity and the like of this light (emission spectrum) 13.

  In addition, laser light is generated from the laser transmitter 16, transmitted using the optical fiber 17, and collected by the collection and collection optical system 18, and identification, measurement and removal of specific nuclides scattered inside the pedestal 5 Examples of the method of irradiating the material 1a as the target and emitting light (emission spectrum) 13 caused by the constituent nuclide and element include a laser induced breakdown method and a laser induced fluorescence method.

  In addition, the laser transmitter 16 can also be used as a laser transmitter for cutting, dissolving, fracturing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5. is there.

  Furthermore, the laser transmitter 16 and a laser for cutting, dissolving, crushing, and decomposing the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 and a laser-induced breakdown method are aimed for It is also possible to separately separately emit a laser and a laser for the purpose of laser induced fluorescence, and to perform irradiation in combination or common use.

  In the present embodiment, the atmosphere environment can be applied to a gas such as air or nitrogen, or to a liquid such as water.

  FIG. 5 shows a modification of the measuring apparatus 7 for measuring the nuclide in FIG. 1 of the first embodiment as the fourth embodiment of the present invention.

  The measuring apparatus 7 for measuring nuclide shown in FIG. 5 comprises a laser transmitter 10 for generating laser light, a first optical fiber 11 for transmitting the laser light generated from the laser transmitter 10, and a first optical fiber 11 Identification, measurement and measurement of specific nuclide that scatters the laser light collected by the first light collection and collection optical system 18a for collecting the transmitted laser light and the laser light collected by the second light collection optical system 18a inside the pedestal 5 The material 1a to be removed is irradiated, and at this time, the introduction tube 22 for introducing the product 21 released from the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 And a pump 23, a measurement cell 24 to which the product 21 is introduced through the introduction pipe 22 and the pump 23, a laser transmitter 16 for generating a second laser beam, and a laser transmitter 16 A second optical fiber 17a for transmitting the second laser light, and a second light collecting member for collecting the second laser light transmitted by the second optical fiber 17a onto the product 21 in the measurement cell 24 The specific nuclide scattered in the interior of the pedestal 5 emitted from the product 21 by focusing the second laser light on the product 21 from the light collecting system 18 b and the second light collecting and collecting optical system 18 b. The component nuclide of the material 1a for the purpose of identification, measurement and removal of light, light (emission spectrum) 25 attributed to the element is collected by the second condensing optical system 18b, and the second optical fiber 17a is used. A beam splitter 19 is provided, which splits the light (emission spectrum) 25 that has been reversely transmitted and returned and transmits the branched light to the evaluation device 9.

  That is, a laser beam is generated from the laser transmitter 10, transmitted using the first optical fiber 11, and condensed by the first condensing optical system 18a, and specific nuclide species scattered in the pedestal 5 The material 1a intended for identification, measurement and removal is irradiated. At this time, from the surface of the material 1 a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5, the product 21 is released by laser irradiation.

  This product 21 is the same as the material 1a for identification, measurement and removal of specific nuclides scattered inside the pedestal 5, and the product 21 is sent to the measurement cell 24 using the introduction pipe 22 and the pump 23 etc. Lead.

  The second laser beam is generated from the second laser transmitter 16 and transmitted using the second optical fiber 17a, and is collected on the product 21 in the measurement cell 24 by the second collection and collection optical system 18b. Let From the product 21, light (emission spectrum) 25 originating from the constituent nuclide and element of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered in the pedestal 5 is emitted.

  The light (emission spectrum) 25 caused by this constituent nuclide and element is collected by the second light collecting and collecting optical system 18b, transmitted using the second optical fiber 17a, and returned (the constituent nuclide, element Light 13) is branched using a beam splitter 19 such as a deflection plate, and a material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside pedestal 5 is Perform identification, measurement and evaluation.

  In addition, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered in the interior of the pedestal 5 is covered with a shatterproof cover 20 to prevent the diffusion of the product 21 emitted from the surface upon laser irradiation. There is. The shatterproof cover 20 is made of a hard material or a flexible material (e.g., rubber, sponge, etc.) compatible with the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5.

  Further, laser light is generated from the laser transmitter 16, transmitted using the second optical fiber 17a, and collected on the product 21 in the measurement cell 24 by the second light collecting and collecting optical system 18b, Laser-induced breakdown method is a method to emit light (emission spectrum) 25 from the constituent 21 of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered from the generation 21 to the inside of the pedestal 5. And laser induced fluorescence.

  In addition, the laser transmitter 16 may be separately irradiated with a laser for laser induced breakdown and a laser for laser induced fluorescence separately, or may be irradiated or implemented in combination with each other. It is.

  In the present embodiment, the atmosphere environment can be applied to a gas such as air or nitrogen, or to a liquid such as water.

  FIG. 6 shows a modification of the measuring apparatus 7 for measuring the nuclide in FIG. 1 of the first embodiment as the fifth embodiment of the present invention.

  The embodiment shown in FIG. 6 shows an embodiment in which the material 1a for the purpose of identifying, measuring and removing specific nuclides scattered inside the pedestal 5 with a high pressure water jet is crushed, broken down and scraped off.

  The measuring apparatus 7 for measuring nuclide shown in FIG. 6 comprises a high pressure water jet pump 26 generating high pressure water jet, a high pressure hose 27 transmitting high pressure water jet generated from the high pressure water jet pump 26, and a high pressure hose 27. High pressure water jet nozzle 28 for focusing transmitted high pressure water jet and high pressure water jet focused by this high pressure water jet nozzle 28 for the purpose of identification, measurement and removal of specific nuclides scattered inside pedestal 5 At this time, the material 1a is sprayed, and at this time, a product (hereinafter simply referred to as a product) generated by crushing, decomposing and scraping from the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 Tube 22 and pump 23 for introducing A measurement cell 24 to which a product 29 is introduced through the introduction pipe 22 and the pump 23, a laser transmitter 16 for generating a laser beam, an optical fiber 17 for transmitting the laser beam generated by the laser transmitter 16, an optical fiber Condensing and collecting optical system 18 for condensing the laser light transmitted at 17 onto the product 29 in the measurement cell 24 and laser light being collected from the condensing and collecting optical system 18 on the product 29 , The component nuclide of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 emitted from the product 29 and light (emission spectrum) 25 attributed to the element The beam splitter 19 is roughly composed of a beam splitter 19 that collects in the system 18 and reverse-transmits it using the optical fiber 17 and branches the returned light (emission spectrum) 25 and transmits it to the evaluation device 9 .

  That is, a high pressure water jet is generated from the high pressure water jet pump 26 and transmitted using the high pressure hose 27 and focused by the high pressure water jet nozzle 28 to identify, measure and remove specific nuclides scattered inside the pedestal 5 The target material 1a is injected. At this time, the material 1a for the purpose of identification, measurement and removal of the specific nuclide scattered inside the pedestal 5 is crushed, broken down, scraped off, and the product 29 is generated.

  This product 29 is the same as the material 1a for identification, measurement and removal of specific nuclides scattered inside the pedestal 5, and the product 29 is introduced to the measurement cell 24 using the introduction tube 22 and the pump 23. . Laser light is generated from the laser transmitter 16, transmitted using the second optical fiber 17a, and collected on the product 29 in the measurement cell 24 by the collection and collection optical system 18. From the product 29, light (emission spectrum) 25 originating from the constituent nuclide and element of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 is emitted.

  The light (emission spectrum) 25 derived from the constituent nuclide and the element is collected by the light collecting and collecting optical system 18, transmitted using the second optical fiber 17a, and returned (the constituent nuclide and the element The light 13) is branched using a beam splitter 19 such as a deflection plate, and the evaluation device 9 carries out identification, measurement and evaluation of specific nuclides.

  In addition, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 is covered with the anti-scattering cover 20 to prevent the diffusion of the product 29 released from the surface during high-pressure water jet injection. doing. The shatterproof cover 20 is made of a hard material or a flexible material (e.g., rubber, sponge, etc.) compatible with the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5.

  In addition, laser light is generated from the laser transmitter 16 and transmitted using the second optical fiber 17a, and is collected on the product 21 in the measurement cell 24 by the light collection and collection optical system 18, and The component nuclide of material 1a for the purpose of identification, measurement and removal of specific nuclide present inside pedestal 5, the method of emitting light (emission spectrum) 25 caused by the element, laser induced breakdown method or laser induced fluorescence There is a law.

  In addition, the laser transmitter 16 may be separately irradiated with a laser for laser induced breakdown and a laser for laser induced fluorescence separately, or may be irradiated or implemented in combination with each other. It is.

  In the present embodiment, another embodiment has been described in which the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 is crushed, disassembled and scraped with the high pressure water jet. Not only jets, but also high pressure high-pressure water jets can crush, disassemble and scrape the material 1a for identification, measurement and removal of specific nuclides scattered inside the pedestal 5.

  In addition, light, heat, sound, ultrasound, vibration, drilling, shock, plasma, mechanical cutting, saw, wear, grinder, core bit, drill, end mill, etc. can be applied as a method that can be crushed, disassembled and scraped off. Therefore, the combination with the present embodiment can be applied.

  In the present embodiment, the atmosphere environment can be applied to a gas such as air or nitrogen, or to a liquid such as water.

  In FIG. 7, the modification of the measuring apparatus 7 which measures the nuclide in FIG. 1 of Example 1 as Example 6 of this invention is shown.

  The embodiment shown in FIG. 7 describes another embodiment in which the material 1a for the purpose of identifying, measuring and removing specific nuclides scattered inside the pedestal 5 with the core bit 32 is crushed, broken down and scraped off.

  A measuring device 7 for measuring nuclide shown in FIG. 7 is provided at a rotary power machine 30 for generating a rotational force, a rotational force transmission shaft 31 for transmitting the rotational force from the rotational power machine 30, and a tip of the rotational force transmission shaft 31. Identification, identification and identification of specific nuclides interspersed in the interior of pedestal 5 by crushing, decomposing, scraping off material 1a for identification and measurement and identification of particular nuclides interspersed in pedestal 5 by this core bit 32 , And the introduction pipe 22 and pump 23 for introducing the product 29 generated by crushing, decomposition, and scraping of the material 1a for the purpose of measurement and removal, and the measurement in which the product 29 is introduced through the introduction pipe 22 and pump 23 A cell 24, a laser transmitter 16 for generating laser light, and a second optical fiber 1 for transmitting the laser light generated from the laser transmitter 16 a, a collection and collection optical system 18 for collecting the laser light transmitted by the second optical fiber 17 a onto the product 29 in the measurement cell 24, and a laser from the collection and collection optical system 18 to the product 29 A light source (element emission spectrum) of the component nuclide of the material 1a for the purpose of identification, measurement and removal of a specific nuclide scattered inside the pedestal 5 emitted from the product 29 by light being collected 25 is collected by the collection and collection optical system 18 and reverse transmitted using the second optical fiber 17a, and the beam splitter 19 which splits the returned light (emission spectrum) 25 and transmits it to the evaluation device 9 It is roughly configured.

  That is, the rotational force of the rotary power machine 30 is transmitted using the rotational force transmission shaft 31, and the core bit 32 is rotated to crush the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5. , Disassemble, scrape. At this time, the material 29 for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 is crushed, broken down, and a scraped product 29 is generated.

  This product 29 is the same as the material 1a for identification, measurement and removal of specific nuclides scattered inside the pedestal 5, and the product 29 is introduced to the measurement cell 24 using the introduction tube 22 and the pump 23. . Laser light is generated from the laser transmitter 16 and transmitted using the second optical fiber 17a, and the collected light is collected by the light collection and collection optical system 18 onto the product 29 in the measurement cell 24. From the product 29, light (emission spectrum) 25 originating from the constituent nuclide and element of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 is emitted.

  The light (emission spectrum) 25 derived from the constituent nuclide and the element is collected by the light collecting and collecting optical system 18, transmitted using the second optical fiber 17a, and returned (the constituent nuclide and the element The light 13) is branched using a beam splitter 19 such as a deflection plate, and the evaluation device 9 carries out identification, measurement and evaluation of specific nuclides.

  In addition, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 is covered with a shatterproof cover 20 to prevent the diffusion of the released product 29. The shatterproof cover 20 is made of a hard material or a flexible material (e.g., rubber, sponge, etc.) compatible with the surface of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5.

  In addition, laser light is generated from the laser transmitter 16 and transmitted using the second optical fiber 17a, and is collected on the product 21 in the measurement cell 24 by the light collection and collection optical system 18, and The component nuclide of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5, the method of emitting the light (emission spectrum) 25 caused by the element, the laser induced breakdown method and the laser induced fluorescence There is a law.

  Furthermore, the laser transmitter 16 may be separately and separately irradiated with a laser for laser induced breakdown and a laser for laser induced fluorescence separately, or may be irradiated and implemented in combination or in common. It is possible.

  The present embodiment is applicable to the atmosphere environment in a gas such as air or nitrogen, or in a liquid such as water.

  FIG. 8 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 7 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, but in the present embodiment, specific nuclide scattered in the outside of the pedestal 5. As a material 1b for the purpose of identification, measurement and removal of

  The method and apparatus for identifying, measuring and evaluating specific nuclides of the material 1b for the purpose of identification, measurement and removal of specific nuclides scattered outside the pedestal 5 in the present embodiment are described in the first to sixth embodiments. The measuring apparatus 7 which measures the radionuclide is applicable, and the combination and application of the said Example are also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 9 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 8 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, but in the present embodiment, specific nuclide scattered in the outside of the pedestal 5. As another example of the material 1b for the purpose of identification, measurement, and removal of C, an example using a remotely operated device (ROV: Remotely Operated Vehicle) 33 is described.

  That is, in the present embodiment, the measuring device 7 for measuring nuclide is installed at the tip of the articulated arm 6 installed in the remote controller 33 which moves in the storage container 3 of the nuclear power generation facility. The concentration or concentration ratio of the material 1b for the purpose of identification, measurement and removal of specific nuclides scattered outside the pedestal 5 of the nuclear power plant measured by the measurement device 7 for measuring nuclide installed at the tip of the Survey, work in nuclear power plant, comparing with target value of concentration or concentration ratio of material 1b for identification, measurement and removal of specific nuclide scattered outside the set pedestal 5 with evaluation device 9 It evaluates and determines the propriety of each work of construction, classification, and taking out.

  The remote controller 33 can be applied to an underwater swimming type, an underwater traveling type, an underwater swimming / running type, a crawler traveling in the air, or the like.

  The method and apparatus for identifying, measuring and evaluating specific nuclides of the material 1b for the purpose of identification, measurement and removal of specific nuclides scattered outside the pedestal 5 in the present embodiment are described in the first to sixth embodiments. The measuring apparatus 7 which measures the radionuclide is applicable, and the combination and application of the said Example are also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 10 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 9 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, but in the present embodiment, it is scattered in the inside of the reactor pressure vessel 4. Another example of the material 1c for the purpose of identification, measurement and removal of specific nuclides is described.

  In the present embodiment shown in the figure, the measuring device 7 for measuring nuclide is installed at the tip of the articulated arm 6 inserted from above the operation floor 46 of the nuclear power plant, and installed at the tip of the articulated arm 6 The concentration or concentration ratio of the material 1c for the purpose of identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 of the nuclear power generation facility measured by the measurement device 7 for measuring The evaluation device 9 compares the target value of the concentration or concentration ratio of the material 1c for the purpose of identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 with the evaluation device 9 for investigation and work in a nuclear power plant It evaluates and determines the propriety of each work of construction, classification, and taking out.

  Although the present embodiment shown in FIG. 10 shows an application example to the central portion (core region) of the reactor pressure vessel 4, the upper position of the reactor pressure vessel 4, the bottom portion of the reactor (the reactor pressure vessel 4) The present invention is applicable to the bottom area) and the lower area outside the furnace bottom area.

  In this embodiment, the method and apparatus for identifying, measuring and evaluating the specific nuclide of the material 1c for the purpose of identification, measurement and removal of the specific nuclide scattered inside the reactor pressure vessel 4 are the same as in Example 1 to Example. The measuring device 7 for measuring the nuclide for measuring the nuclide described in 6 is applicable, and the combination and application of the above embodiments are also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 11 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 10 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the pedestal 5. However, in the present embodiment, the upper portion of the inside of the reactor pressure vessel 4 is described. Another example of the material 1 d for the purpose of identification, measurement and removal of specific nuclides present on the separator 34 and the dryer 35 in FIG.

  In the present embodiment shown in the figure, the measuring device 7 for measuring nuclide is installed at the tip of the articulated arm 6 inserted from above the operation floor 46 of the nuclear power plant, and installed at the tip of the articulated arm 6 Concentration of material 1d for the purpose of identification, measurement and removal of specific nuclides scattered inside the separator 34 and the dryer 35 at the top of the reactor pressure vessel 4 of the nuclear power plant measured by a measuring device for measuring Alternatively, the evaluation device 9 compares the concentration ratio with the target value of the concentration or concentration ratio of the material 1 d for the purpose of identification, measurement and removal of the specific nuclide scattered inside the separator 34 and the dryer 35 set in advance. Evaluate / determine whether or not each operation in nuclear power facilities is to be surveyed, worked, constructed, sorted, and taken out.

  In the present embodiment shown in FIG. 11, another embodiment directed to a material 1d for the purpose of identification, measurement and removal of specific nuclides present on the separator 34 and the dryer 35 at the upper part inside the reactor pressure vessel 4 In this embodiment, the present invention can be applied to the whole area of the reactor pressure vessel 4, the whole area of the containment vessel 3, the whole area of the nuclear power building 2, the whole area of the nuclear power plant and the whole area outside the nuclear power plant. is there.

  In this embodiment, the method and apparatus for identifying, measuring and evaluating specific nuclides of the material 1 d for the purpose of identification, measurement and removal of specific nuclides present on the separator 34 and the dryer 35 and present are the same as in the first embodiment. The measuring device 7 for measuring nuclide described in 6 is applicable, and the combination and application of the above embodiments are also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 12 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 11 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, but in the present embodiment, specific nuclide scattered in the interior of the pedestal 5. Another example of the material 1a for the purpose of identification, measurement and removal of

  In the present embodiment shown in the figure, the holding device 36 for holding the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5 is from the outside of the containment vessel 3 of the nuclear power plant. The purpose is to identify, measure and remove specific nuclides scattered inside the pedestal 5 installed at the tip of the articulated arm 6 to be inserted and gripped by the gripping device 36 installed at the tip of the articulated arm 6 The concentration or concentration ratio of the material 1a is measured by the measuring device 7, and the material 1a for the purpose of identification, measurement and removal of the specific nuclide scattered inside the pedestal 5 of the nuclear power plant measured by the measuring device 7 Concentration or concentration ratio and target value of concentration or concentration ratio of material 1a for identification, measurement and removal of specific nuclide scattered inside pedestal 5 of preset nuclear power plant Compared with value device 9, investigation in a nuclear power facility, work, work, separation, is designed to measure the evaluation and determining nuclides permission for the work of the take-out.

  That is, as shown in FIG. 12, the articulated arm 6 is inserted from the outside of the storage container 3, and at the tip of the articulated arm 6, a gripping device 36, a suction device, etc. are installed. The articulated arm 6 is stored in the cell 8 and airtightness is maintained.

  Then, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 is gripped or suctioned or transferred by the gripping device 36, guided to the cell 8, transported to the sorting cell 37 and introduced. Material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 carried and introduced into the sorting cell 37 is identified and measured by the measurement device 7 for measuring nuclide. In the evaluation device 9, identification, measurement and evaluation of nuclide are performed.

  Based on the evaluation result by the evaluation device 9, identification, measurement and removal of a specific nuclide of the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered in the pedestal 5 are performed.

  The apparatus for identifying, measuring and evaluating the specific nuclide of the material 1a for the purpose of identification, measurement and removal of the specific nuclide scattered inside the pedestal 5 in the present embodiment is the nuclide described in the first to sixth embodiments. The measuring device 7 which measures the is applicable, and the combination with those above-mentioned examples is also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 13 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 12 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, but in the present embodiment, it is scattered in the inside of the reactor pressure vessel 4. Another example of the material 1c for the purpose of identification, measurement and removal of specific nuclides is described.

  In the present embodiment shown in the figure, the gripping device 36 for gripping the material 1c for the purpose of identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 is from above the operation floor 46 of the nuclear power plant. Identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 installed at the tip of the articulated arm 6 to be inserted and gripped by the gripping device 36 installed at the tip of the articulated arm 6 The concentration or concentration ratio of the target material 1c is measured by the measuring device 7, and identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 of the nuclear power plant measured by the measuring device 7 are performed. The concentration or concentration ratio of the target material 1c, and the concentration of the material 1c for the purpose of identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 of a preset nuclear power facility By comparing the target value of the concentration ratio in the evaluation apparatus 9, research in nuclear power plants, work, construction work, fractionation, is to evaluate and determine the propriety of the work of the extraction.

  That is, as shown in FIG. 13, the multi-joint arm 6 is inserted from above the operation floor 46 which is the outside of the storage container 3, and the multi-joint arm 6 is provided with a gripping device 36, a suction device, a transfer device, etc. There is. The articulated arm 6 is stored in the cell 8 and airtightness is maintained.

  Then, the material 1c for the purpose of identification, measurement and removal of specific nuclides present inside the reactor pressure vessel 4 is gripped, sucked or transferred by the gripping device 36 and passed through the cell 8 to the sorting cell 37 Transport, introduce. Material 1c for the purpose of identification, measurement and removal of specific nuclide scattered inside the reactor pressure vessel 4 transported and introduced into the inside of the fractionation cell 37 is identification of the specific nuclide by the measuring device 7 which measures nuclide, Measurement is performed, and identification, measurement and evaluation of nuclide are performed in the evaluation device 9.

  Identification, measurement and removal of a specific nuclide of the material 1 c for the purpose of identification, measurement and removal of specific nuclide scattered in the interior of the reactor pressure vessel 4 are performed based on the evaluation result by the evaluation device 9.

  In this embodiment, the method and apparatus for identifying, measuring and evaluating the specific nuclide of the material 1c for the purpose of identification, measurement and removal of the specific nuclide scattered inside the reactor pressure vessel 4 are the same as in Example 1 to Example. The measuring device 7 for measuring the nuclide described in 6 is applicable, and the combination with those embodiments is also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 14 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 13 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5, but in the present embodiment, specific nuclide scattered in the interior of the pedestal 5. Another example of the material 1a for the purpose of identification, measurement and removal of

  In this embodiment shown in the figure, the suction device 38 for suctioning the material 1a for the purpose of identification, measurement and removal of specific nuclide scattered in the interior of the pedestal 5 is from the outside of the containment vessel 3 of the nuclear power generation facility. Aimed at identification, measurement and removal of specific nuclide scattered inside the pedestal 5 installed at the tip of the articulated arm 6 to be inserted and sucked by the suction device 38 installed at the tip of the articulated arm 6 The concentration or concentration ratio of the material 1a is measured by the measuring device 7, and it is intended to identify, measure and remove specific nuclides scattered inside the pedestal 5 scattered inside the pedestal of the nuclear power plant measured by the measuring device 7. The concentration or concentration ratio of the material 1a, and the target of the concentration or concentration ratio of the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the preset pedestal 5 Compare the door in the evaluation device 9, investigation in a nuclear power facility, work, work, separation, is intended to assess and determine the propriety of the work of the take-out.

  That is, as shown in FIG. 14, the multi-joint arm 6 is inserted from the outside of the storage container 3, and a suction device 38 or the like is installed at the tip of the multi-joint arm 6. The introduction tube 39 is provided to transport and introduce the material 1a for identification, measurement and removal of specific nuclides scattered inside the pedestal 5 through the cell 8 into the sorting cell 37. The articulated arm 6 is stored in the cell 8 and airtightness is maintained.

  The material 1a for the purpose of identification, measurement and removal of specific nuclide scattered inside the pedestal 5 carried and introduced into the sorting cell 37 is identification and measurement of the specific nuclide by the measuring device 7 for measuring nuclide Is performed, and identification, measurement and evaluation of nuclide are performed by the evaluation device 9 ′.

  Based on the evaluation result by the evaluation device 9 ′, identification, measurement and removal of a specific nuclide of the material 1 a for the purpose of identification, measurement and removal of specific nuclide dispersed in the pedestal 5 are performed.

  The identification, measurement and evaluation device 9 'of this specific nuclide is a device characterized by evaluation using, for example, a chemical decomposition device, ICP-MS, ICP-AES or the like. The material 1a for the purpose of identification, measurement and removal of specific nuclides scattered in the interior of the pedestal 5 is adaptable whether the atmosphere environment is a gas such as air or nitrogen or a liquid such as water.

  Also, when evaluating the material 1a with reference to the emission spectrum of the measured material 1a, the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered inside the pedestal 5 is to be evaluated. Derivation of specific nuclides for the purpose is carried out by suction in liquid or air, or by suction and holding using a microdevice.

  The method and apparatus for identifying, measuring and evaluating specific nuclides of the material 1 a for identification, measurement and removal of specific nuclides scattered inside the pedestal 5 in the present embodiment are described in the first to sixth embodiments. The measuring apparatus 7 which measures the radionuclide is applicable, and the combination with those above-mentioned examples is also possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 15 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 14 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered inside the pedestal 5. However, in the present example, the specific nuclide in the waste storage 40 is Examples of the material 1e intended for identification, measurement and removal are described.

  In the present embodiment shown in the figure, a holding device 36 for holding the material 1c for the purpose of identification, measurement and removal of specific nuclides scattered inside the reactor pressure vessel 4 or a pedestal of a nuclear power generation facility of a nuclear power generation facility The gripping device 36 for gripping the material 1a for the purpose of identification, measurement and removal of specific nuclides scattered in the interior of the 5 is from the operation floor 46 of the nuclear power plant or from the outside of the containment vessel 4 of the nuclear power plant The material 1c or 1a installed at the tip of the articulated arm 6 to be inserted and held by the gripping device 36 installed at the tip of the articulated arm 6 is stored in the waste storage 40 of the nuclear power generation facility. The concentration or concentration ratio of the material 1e stored in the waste storage 40 is measured by the measuring device 7, and the material 1e in the waste storage 40 measured by the measuring device 7 Based on this evaluation result, the concentration or concentration ratio is compared with the target value of the concentration or concentration ratio of the material 1e for the purpose of identification, measurement, and removal of the specific nuclide set in advance, and evaluation is performed. As to what to evaluate, whether it contains nuclear fuel, whether it contains α-type, whether it is treated as α-waste, whether it is treated as general waste, whether it is treated as nuclear fuel material, as fuel debris Whether to handle fuel debris and waste separation, nuclear fuel and waste separation, radionuclides for measurement control and other separations, safeguards for radionuclides and other separation and evaluation are possible. is there.

  That is, as shown in FIG. 15, the material 1c for the purpose of identification, measurement and removal of specific nuclides present inside the reactor pressure vessel 4 is installed on the upper part of the nuclear building 2 (at the level of the operation floor 46). The storage can 41 is transferred to the receiving cell 43 in the waste storage 40 and transferred to the sorting cell 37.

  The material 1e for the purpose of identification, measurement and removal of specific nuclide in the waste storage 40 in the sorting cell 37 is identified and measured by the measurement device 7 for measuring nuclide, and evaluation device The identification, measurement and evaluation of nuclide are carried out at 9.

  Based on the evaluation result by this evaluation device 9, identification of specific nuclide in waste storage 40, measurement and identification of specific nuclide of material 1e for the purpose of removal and measurement are carried out, nuclear fuel 44 and general waste 45 It can be separated.

  Whether nuclear fuel is included or not, whether it is included as alpha waste, whether it is treated as alpha waste, whether it is treated as general waste, whether it is desired to evaluate based on the identification, measurement and evaluation results of the specific nuclide Whether or not it is handled as nuclear fuel material, whether or not it is handled as fuel debris, fuel debris and waste separation, nuclear fuel and waste separation, target nuclide and other classification of measurement control, safeguards target nuclide and other It can be separated and evaluated, and can be separated into nuclear fuel 44 and general waste 45.

  In Examples 1 to 14 and this example, the apparatus for identifying, measuring and evaluating the specific nuclide of the material 1 for the purpose of identification, measurement and removal of specific nuclide is the same as described in Example 1 to Example 6. While the measurement apparatus 7 which measures nuclide is applicable, XPS method (X-ray electron spectroscopy) is also applicable as the measurement apparatus 7 of Example 1- Example 14, and ICP-MS (inductive plasma mass spectrometry) Device), ICP-AES (inductive plasma emission spectrometry), XPS method (X-ray electron spectroscopy), EDS method (energy dispersive X-ray analysis method), or WDS method (wavelength dispersive X-ray analysis method) These measuring devices are also applicable as the measuring devices 7 of Examples 1 to 14, and combinations of these measuring devices and measuring devices 7 and various combinations with each other, their respective measurements Device and combination of the above embodiments are possible.

  The effect of this embodiment is the same as that of the first embodiment.

  FIG. 16 shows a method of separating nuclear fuel nuclides and a nuclear power plant to be subjected to the apparatus as Example 15 of the present invention.

  In FIG. 1 of the first embodiment described above, the material 1a has been described as the material 1a for identification, measurement and removal of specific nuclide scattered inside the pedestal 5. However, in the present example, the specific nuclide in the waste storage 40 is Another example (modification of Example 14) to the material 1e for identification, measurement and removal is described.

  That is, in the present embodiment, as shown in FIG. 16, the measuring apparatus 7 ′ for measuring nuclide is stored in the entire area of the reactor pressure vessel 4, the entire area of the containment vessel 3, the entire area of the nuclear building 2, waste storage It can be installed and applied to the entire interior of the storage 40, the entire nuclear power plant, and the entire area outside the nuclear power plant.

  The measuring apparatus 7 'for measuring the nuclide can be applied to the measuring apparatus 7 for measuring the nuclide described in the first to sixth embodiments, and a combination with the above embodiments is also possible.

  The present embodiment is applicable to the atmosphere environment in a gas such as air or nitrogen, or in a liquid such as water.

  In this embodiment, in an apparatus characterized by evaluating a specific nuclide by focusing on the specific nuclide and emission spectrum in detection, measurement and monitoring of a specific nuclide, a material for identification, measurement and removal of the specific nuclide ( Identification and identification of specific nuclides described above by applying or installing the detection, identification, measurement and monitoring of nuclides and specific nuclides in the entire space, gas phase, liquid phase and other areas of the target facility. Detection, identification, measurement and monitoring of materials (nuclides) and specific nuclides for the purpose of measurement and removal, and detection, identification, measurement and monitoring of specific nuclides etc. specific nuclide concentrations and their target values As compared with the above, we evaluate and judge whether it is necessary for workers to enter and for evacuation in case of emergency, evacuation in case of accident, and when evacuation is necessary, it is avoided. Alarm the alarm and evacuation instructions, it is possible to issued.

  FIG. 17 shows the flow in the identification, measurement and evaluation apparatus 9 of the specific nuclide described in Examples 1 to 15 as Example 16 of the present invention.

  As shown in FIG. 17, the identification, measurement and evaluation device 9 of the specific nuclide collects concentration information of the material 1a for the purpose of identification, measurement and removal of the specific nuclide from the device 7 for measuring nuclide, The density ratio is calculated, corrected and evaluated (S1), and the evaluation value is evaluated (S2). Compare this evaluation value (S2) with the reference value (S3), which is the target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of specific nuclide stored in the database 47 To do (S4). The identification, measurement and evaluation device 9 of the specific nuclide compares the evaluation value (S2) with the reference value (S3), and examines whether or not the operation can be performed (S5). The identification, measurement and evaluation unit 9 of the specific nuclide outputs the result of the availability determination (S6), determines the execution of the work (S7) or the stop of the work (S8), and instructs and outputs it.

  FIG. 18 shows the flow in another example of the identification, measurement and evaluation apparatus 9 of the specific nuclide described in Examples 1 to 15 as Example 17 of the present invention.

  As shown in FIG. 18, the identification, measurement and evaluation device 9 of the specific nuclide of the present embodiment collects concentration information of the material 1a for the purpose of identification, measurement and removal of the specific nuclide from the device 7 for measuring nuclide. Then, the concentration or concentration ratio is calculated, corrected and evaluated (S1), and the evaluation value is evaluated (S2). Compare this evaluation value (S2) with the reference value (S3), which is the target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of specific nuclide stored in the database 47 To do (S4). The identification, measurement and evaluation unit 9 of the specific nuclide compares the evaluation value (S2) with the reference value (S3), examines it to determine the presence or absence of the material 1a for the purpose of identification, measurement and removal of the specific nuclide. The evaluation value and the determination result are output (S9). This output maps and records the presence distribution of the material 1a for the purpose of identification, measurement and removal of specific nuclide (S10).

  As a result, progress, information management of each work of investigation, work, construction, sorting, and taking out, storage and storage of implementation record, estimation of necessary preparation work, storage and storage of accident situation become possible.

  FIG. 19 shows the flow of the embodiment relating to the executability of each work such as investigation, construction, sorting, and taking out as described in the embodiment 1 to the embodiment 17 as the embodiment 18 of the present invention.

  As shown in FIG. 19, the concentration information of the material 1a for the purpose of identification, measurement and removal of specific nuclide is collected using the apparatus 7 for measuring nuclide (S11), and identification, measurement and evaluation of the specific nuclide Identification, measurement and evaluation of specific nuclides are carried out using 9 (S12). The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide It compares with a certain reference value and judges (S13).

  Based on the result, it is judged, instructed, and output of execution of work or cancellation of work (S14). If the work can be performed (for example, evaluation value <reference value), the work is performed and continued (S15). If the work can not be executed (for example, evaluation value> reference value), the work is stopped (S16). Furthermore, when it is determined that the work can not be performed, the work improvement is performed after stopping the work (S17), and identification and measurement of a specific nuclide using the nuclide measuring apparatus 7 again. And the concentration information of the material 1a intended for removal is collected (S11), and identification, measurement and evaluation of the specific nuclide are carried out using the identification, measurement and evaluation device 9 of the specific nuclide (S12).

  The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide It compares with a certain reference value and judges (S13).

  Based on the result, it is judged, instructed, and output of execution of work or cancellation of work (S14).

  Work improvement (S17) includes boric acid injection, increased injection of boric acid concentration, restriction of working area, exclusion of water in working area, handling of material 1a for the purpose of identification, measurement and removal of specific nuclides Implement volume restrictions etc.

  In FIG. 20, as the nineteenth embodiment of the present invention, the embodiment related to the executability of each work such as the investigation, the construction, the sorting, the taking out and the like described in the first to eighteenth embodiments and the warning of warning issuance and evacuation. Shows the flow.

  The target areas for warning of warning and evacuation for this embodiment are the inside of the building, cells installed in the building indoor part, the building installed outside the building and the facility site in the building outside part, building outside part Inside, outside the facility site, surrounding resident area, etc. are targeted areas.

  As shown in FIG. 20, the concentration information of the material 1a for the purpose of identification, measurement and removal of specific nuclides is collected using the apparatus 7 for measuring nuclide (S11), and identification, measurement and evaluation of specific nuclides Identification, measurement and evaluation of specific nuclides are carried out using 9 (S12). The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide It compares with a certain reference value and judges (S13).

  Based on the result, it is judged, instructed, and output of execution of work or cancellation of work (S14). If the work can be performed (for example, evaluation value <reference value), the work is performed and continued (S15). If the work can not be executed (for example, evaluation value> reference value), the work is stopped (S16). Furthermore, if the task can not be executed, and the target area for issuing a warning (described above) is a status where a warning should be issued (for example, evaluation value> reference value), the task To issue a warning and warning of evacuation to the target area that is required after canceling the operation (S18).

  Again, the concentration information of the material 1a for the purpose of identification, measurement and removal of specific nuclides is collected using the nuclide measuring apparatus 7 (S11), identification of the specific nuclides, identification using the measurement and evaluation apparatus 9 The identification, measurement and evaluation of nuclide are carried out (S12). The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide It compares with a certain reference value and judges (S13).

  Based on the result, it is judged, instructed, and output of execution of work or cancellation of work (S14). If the work can be performed (for example, evaluation value <reference value), the work is performed and continued (S15). If the work can not be executed (for example, evaluation value> reference value), the work is stopped (S16). Furthermore, it is necessary if the work can not be performed, the warning issuance warning, the target area for evacuation issuance (described above) is the state for warning issuance, evacuation should be issued (for example, evaluation value> reference value). Issue an alert to the target area, and issue an evacuation order (S18).

  In FIG. 21, as Example 20 of the present invention, materials for the purpose of identification, measurement and removal of specific nuclide as to whether or not each work such as investigation, construction, separation, extraction etc. is described in Examples 1 to 19 Fig. 6 shows the flow of an embodiment related to mapping and recording of the distribution of existence of C, storage, and completion of each operation.

  As shown in FIG. 21, using the apparatus 7 for measuring nuclide, concentration information of the material 1a for the purpose of identification, measurement and removal of specific nuclide is collected (S11), and identification, measurement and evaluation apparatus of specific nuclide Identification, measurement and evaluation of specific nuclides are carried out using 9 (S12). The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide It compares with a certain reference value and judges (S13).

  Based on the result, it is judged, instructed, and output of execution of work or cancellation of work (S14). If the work can be performed (for example, evaluation value <reference value), the work is performed and continued (S15). If the work can not be performed (for example, evaluation value> reference value), the work is stopped (S16). If it is determined that the work can not be performed, work improvement is performed as necessary after stopping the work (S17), and identification, measurement and removal of specific nuclide using the nuclide measuring apparatus 7 again The concentration information of the material 1a of interest is collected (S11), and identification, measurement and evaluation of the specific nuclide are carried out using the identification, measurement and evaluation device 9 of the specific nuclide (S12). The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide It compares with a certain reference value and judges (S13).

  Based on the result, it is judged, instructed, and output of execution of work or cancellation of work (S14).

  Work improvement (S17) includes boric acid injection, increased injection of boric acid concentration, restriction of working area, exclusion of water in working area, handling of material 1a for the purpose of identification, measurement and removal of specific nuclides Implement volume restrictions etc.

  Then, in the present embodiment, when it is possible to carry out the work, the work is carried out (S15), and the concentration of the material 1a for the purpose of identification, measurement and removal of specific nuclides using the apparatus 7 for measuring nuclides Information is collected (S11 '), the concentration or concentration ratio is calculated, corrected and evaluated using the identification, measurement and evaluation device 9 of the specific nuclide, and the evaluation value is evaluated (S12'). The target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide stored in the evaluation value and database 47 in the identification, measurement and evaluation unit 9 of the specific nuclide The evaluation value and the determination result are output together with the determination of the presence or absence of the material 1a for the purpose of identification, measurement and removal of the specific nuclide by comparison with a certain reference value and determination (S13 ').

  This output is stored by mapping and recording the presence distribution of the material 1a for the purpose of identification, measurement and removal of a specific nuclide (S19). From the determination result of the presence or absence of the material 1a for the purpose of identification, measurement and removal of the specific nuclide, the completion of the work is determined (S14 '). If it is determined in the step (S14 ') that the work completion is No, the process returns to the step (S15), and the steps (S15) to (S14') are performed.

  Also, based on the mapping results of the presence distribution of the material 1a for the purpose of identification, measurement and removal of specific nuclide, confirmation of the presence and location of the remaining area considered necessary for the work and the completion of the whole work It can be judged and confirmed.

  From this result, progress, information management of each work of investigation, work, construction, sorting, and taking out, storage and storage of implementation record, estimation of necessary preparation work, storage and storage of accident situation, work are considered necessary It is possible to confirm the presence or absence of the area left and the completion of the entire work.

  The present invention is not limited to the embodiments described above, but includes various modifications. For example, the embodiments described above are described in detail in order to explain the present invention in an easy-to-understand manner, and are not necessarily limited to those having all the configurations described. Also, part of the configuration of one embodiment can be replaced with the configuration of another embodiment, and the configuration of another embodiment can be added to the configuration of one embodiment. In addition, with respect to a part of the configuration of each embodiment, it is possible to add, delete, and replace other configurations.

  1a: Material for identification, measurement and removal of specific nuclides dispersed inside pedestal, 1b: material for identification, measurement and removal of specific nuclides scattered outside of pedestal, 1c: reactor pressure vessel Material for the purpose of identification, measurement and removal of specific nuclides scattered inside of the material, 1d: Adherence to separators and dryers, material for identification of specific nuclides present, measurement and removal, 1e in waste storage Materials for identification, measurement and removal of specific nuclides, 2. Nuclear building, 3. Containment vessel, 4. Reactor pressure vessel, 5. Pedestal, 6. Multi-joint arm, 7, 7 ': Measuring nuclides Device 8: cell 9: identification of specific nuclide, measurement and evaluation device 10, 16: laser oscillator 11: first optical fiber 12: focusing optical system 13, 25: same of specific nuclide , Constituent nuclide of material intended for measurement and removal, light due to element (emission spectrum), 14 ... collection optics, 15 ... second optical fiber, 17 ... optical fiber, 17 a ... second optical fiber, 18 ... Focusing collection optical system, 18a: first focusing collection optical system, 18b: second focusing collection optical system, 19: beam splitter, 20: scattering prevention cover, 21: surface upon laser irradiation 22: Introductory tube, 23: Pump, 24: Measurement cell, 26: High pressure water jet pump, 27: High pressure hose, 28: High pressure water jet nozzle, 29: Identification, measurement and removal of specific nuclides Aims at crushing, disassembling, scraping off materials, 30 ... rotational power machine, 31 ... rotational force transmission shaft, 32 ... core bit, 33 ... remote controller, 34 ... separator, 35 ... de Ears 36: gripping devices 37: sorting cells 38: suction devices 39: introduction pipes 40: waste storage containers 41: storage cans 42: transfer casks 43: receiving cells 44: nuclear fuel 45: General waste, 46 ... operation floor, 47 ... database.

Claims (24)

  The concentration or concentration ratio of a material (specific nuclide) for the purpose of identification, measurement and removal of specific nuclide scattered in facilities using nuclear fuel, general nuclear facilities or nuclear facilities where an accident occurred A method of separating nuclear fuel nuclides characterized by evaluating / determining whether or not each operation of survey, work, construction, sorting, and taking out in said facility based on the concentration or concentration ratio of In the method for separating nuclear fuel nuclides according to claim 1,
Concentration or concentration ratio of material (specific nuclide) for identification, measurement and removal of the specific nuclide measured and material (specific nuclide) for identification, measurement and removal of the specific nuclide preset A device is provided for comparing the concentration or concentration ratio with a target value, and the device compares the concentration or concentration ratio of the material with a preset target value of the concentration or concentration ratio in the facility, and A method of separating nuclear fuel nuclides characterized by evaluating / determining whether or not each operation of inspection, work, construction, sorting, and taking out. In the method for separating nuclear fuel nuclides according to claim 1 or 2,
The concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide is the nuclear fuel nuclide and the nuclide present in the facility, the nuclide having the effect of suppressing the critical phenomenon and the nuclide present in the facility, A method of separating nuclear fuel nuclides characterized in that the nuclear fuel nuclides present in the facility or the nuclear fuel nuclides and the nuclides having a suppressing effect on critical phenomena. In the method for separating nuclear fuel nuclides according to any one of claims 1 to 3,
Materials for the purpose of identification, measurement and removal of the specific nuclide are the specific nuclide, α nuclide U, Pu, Am, Np contained in nuclear fuel, nuclear fuel nuclide U, Pu of safeguards target, and the effect of suppressing critical phenomena Radionuclides Gd, B, Hf, Sm, radionuclides Cs, Sr, I, Co, T, Eu, Tc, Ru, Ce, radionuclides Si, Ca, Mg, Al, Fe, Zr, Hf, existing in facilities It is Ni, Cr, Mn, Mo, Nb, Ta, and Ti, The separation method of nuclear fuel nuclide characterized by the above-mentioned. In the method for separating nuclear fuel nuclides according to any one of claims 1 to 4,
Target value of concentration ratio of material (specific nuclide) intended for identification, measurement and removal of the specific nuclide set in advance and concentration ratio of at least two nuclide of the material for identification, measurement and removal of the specific nuclide And a device for comparing the concentration ratio of at least two or more species of the material with the target value of the concentration ratio of the material set in advance in the device, the survey, work, construction, and the like in the facility A method of separating nuclear fuel nuclides characterized by evaluating / determining whether or not each operation of separation and extraction is performed. In the method for separating nuclear fuel nuclides according to claim 5,
At least two or more nuclides for identification, measurement, and removal of the specific nuclide are specific nuclide, which are specific nuclide, alpha nuclide U, Pu, Am, Np included in nuclear fuel, nuclear fuel nuclide U, Pu of safeguards object, critical phenomenon Nuclides Gd, B, Hf, Sm, radionuclides Cs, Sr, I, Co, T, Eu, Tc, Ru, Ce, nuclides Si, Ca, Mg, Al, Fe, Zr present in facilities Hf, Ni, Cr, Mn, Mo, Nb, Ta, and Ti are ratios of at least two or more nuclides, and the concentration ratio of these nuclides or more is compared with a preset target value in the facility. A method of separating nuclear fuel nuclides characterized by evaluating / determining whether or not each operation of inspection, work, construction, sorting, and taking out. In the method for separating nuclear fuel nuclides according to any one of claims 1 to 6,
When measuring a material for the purpose of identification, measurement and removal of the specific nuclide, the material is evaluated with reference to the emission spectrum of the material, or the identification, measurement and removal of the specific nuclide are aimed for When measuring a material, the material is irradiated with a laser, and the material is evaluated with reference to the emission spectrum of the material emitted at that time, or the material is irradiated with a laser to cut the material of interest A method of separating nuclear fuel nuclides, characterized in that the material is evaluated with reference to the emission spectrum of the material emitted at that time. In the method of separating nuclear fuel nuclides according to any one of claims 1 to 7,
After evaluating the material aiming at identification, measurement and removal of the specific nuclide, the specific nuclide and specific nuclide for the purpose of evaluating and judging the presence of the specific nuclide aiming at removal from the evaluated amount, and removing are included A method of separating nuclear fuel nuclides characterized by evaluating and confirming the absence of an object or evaluating and confirming the completion of the removal and removal of material for the purpose of identification, measurement and removal of specific nuclides. The method for separating nuclear fuel nuclides according to any one of claims 1 to 8.
When measuring the material for the purpose of identification, measurement and removal of the specific nuclide and evaluating the material with reference to the emission spectrum of the material, the derivation of the specific nuclide for the evaluation is in liquid or Aspiration in air or by suction and holding using a microdevice, or
Or when measuring a material for the purpose of identification, measurement and removal of the specific nuclide and evaluating the material with reference to the emission spectrum of the material, identification, measurement and removal of the specific nuclide in the vicinity of the material A measuring device is provided to measure and evaluate the concentration of a target material or an nuclide having a suppressing effect on a critical phenomenon, and the concentration is measured and evaluated by the measuring device, based on the concentration or concentration ratio thereof. A method of separating nuclear fuel nuclides characterized by evaluating and judging whether or not the execution, continuation, and execution of each work of survey, work, construction, sorting, and taking out in the facility. In the method of separating nuclear fuel nuclides according to any one of claims 1 to 9,
When measuring a material for identification, measurement and removal of the specific nuclide, and evaluating the material with reference to the emission spectrum of the material, a material for identification, measurement and removal of the specific nuclide and Specific nuclides, alpha nuclides U, Pu, Am, Np contained in nuclear fuel, nuclear fuel nuclides U, Pu subject to safeguards, nuclides Gd, B, Hf, Sm, which have the effect of suppressing critical phenomena, radionuclides Cs, Sr , I, Co, T, Eu, Tc, Ru, Ce, emission intensities of nuclide Si, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr, Mn, Mo, Nb, Ta, Ti existing in facilities A method of separating nuclear fuel nuclides characterized by referring to the ratio of The method for fractionating nuclear fuel nuclides according to any one of claims 1 to 10.
When measuring a material for identification, measurement and removal of the specific nuclide, and evaluating the material with reference to the emission spectrum of the material, a material for identification, measurement and removal of the specific nuclide and Specific nuclides, alpha nuclides U, Pu, Am, Np contained in nuclear fuel, nuclear fuel nuclides U, Pu subject to safeguards, nuclides Gd, B, Hf, Sm, which have the effect of suppressing critical phenomena, radionuclides Cs, Sr , I, Co, T, Eu, Tc, Ru, Ce, Measurement places of nuclide Si, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr, Mn, Mo, Nb, Ta, Ti existing in facilities Alpha nuclide contained in nuclear fuel, which is a material and specific nuclide intended to identify, measure and remove the specific nuclide at the location by adapting and installing in the entire space of the target facility, the gas phase part and the entire liquid phase part U, Pu, Am , Np, nuclear fuel nuclides U and Pu subject to safeguards, nuclides Gd, B, Hf and Sm, which have the effect of suppressing critical phenomena, radionuclides Cs, Sr, I, Co, T, Eu, Tc, Ru, Ce, etc. Measurement of nuclides Si, Ca, Mg, Al, Fe, Zr, Hf, Ni, Cr, Mn, Mo, Nb, Ta, Ti existing in the facility, or the concentration of specific Evaluate / determine whether or not the execution, investigation, work, separation, separation, and execution of each work in the facility will be performed or compared with the set target value, or evaluate / determine whether or not the worker can enter Nuclear fuel, which evaluates and determines whether or not workers need to enter and evacuate in an emergency or in case of an accident, and issue an evacuation warning or an evacuation instruction if evacuation is necessary. Method of separating nuclides. The method for separating nuclear fuel nuclides according to any one of claims 1 to 11.
Materials for the purpose of identification, measurement and removal of the specific nuclides include materials scattered inside and outside of the pedestal of the nuclear power generation facility, materials scattered inside the reactor pressure vessel of the nuclear power generation facility, separators of the nuclear power generation facility, A method of separating nuclear fuel nuclides characterized in that the material is either attached to or scattered in the dryer or in the waste storage of a nuclear power generation facility. Measurement equipment for measuring the concentration or concentration ratio of materials (specific nuclides) for the purpose of identification, measurement and removal of specific nuclides scattered in facilities using nuclear fuel, general nuclear facilities or nuclear facilities that have caused an accident, or A gripping device to be gripped, a measuring device for measuring the concentration or concentration ratio of the material gripped by the gripping device, a suction device for sucking the material, and a concentration or concentration ratio of the material sucked by the suction device Measuring device,
The measuring device, or a gripping device for gripping the material, a measuring device for measuring the concentration or concentration ratio of the material gripped by the gripping device, a suction device for sucking the material, and the suctioned by the suction device An evaluation device which evaluates / determines whether or not each operation of survey, work, construction, sorting, and extraction in the facility is based on the concentration of the material measured by the measurement device which measures the concentration or concentration ratio of the material; An apparatus for separating nuclear fuel nuclides characterized by comprising. In the apparatus for separating nuclear fuel nuclides according to claim 13,
The measuring device is installed at the tip of an articulated arm inserted from the lateral outside of the containment vessel of the nuclear power generation facility, and the measuring device of the nuclear power facility measured by the measuring device installed at the tip of the articulated arm The specific nuclide scattered inside and outside the pedestal,
A pedestal of the nuclear power generation facility, which is installed at the tip of an articulated arm installed on a remote controller moving in a containment vessel of a nuclear power generation facility and measured by the measuring device installed at the tip of the articulated arm The specific nuclide scattered inside and outside,
Alternatively, the inside and the outside of the reactor pressure vessel of the nuclear power plant measured by the measuring device installed at the tip of the articulated arm inserted from the operation floor of the nuclear power plant and installed at the tip of the articulated arm Said specific nuclide scattered in
Alternatively, the separator of the reactor pressure vessel of the nuclear power generation facility, which is installed at the tip of the articulated arm inserted from the operation floor of the nuclear power generation facility and measured by the measuring device installed at the tip of the articulated arm And / or concentration or concentration ratio of material (specific nuclide) for identification, measurement and removal of the specific nuclide scattered inside and outside the dryer, and identification, measurement and removal of the specific nuclide set in advance The target value of concentration or concentration ratio of the material (specific nuclide) to be compared is compared with the evaluation device to evaluate / determine whether or not each operation of survey, work, construction, sorting, and extraction in the facility is possible. Separation equipment for nuclear fuel nuclides. In the apparatus for separating nuclear fuel nuclides according to claim 13,
The suction device for sucking in the material for the purpose of identification, measurement and removal of the specific nuclide, or the gripping device for gripping is an articulated arm inserted from the outside of the containment vessel of the nuclear power plant, or a nuclear power plant The concentration or concentration ratio of the material held by the suction device installed at the tip of the articulated arm inserted from the top of the operation floor and held by the grasping device by the suction device installed at the tip of the articulated arm Materials for the purpose of identification, measurement and removal of the specific nuclide scattered inside and outside the pedestal of the nuclear power facility or inside and outside the reactor pressure vessel measured by the device and measured by this measurement device And the target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide preset in advance. Compared with valence apparatus, the study in the facility, work, construction work, sorting, sorter nuclear fuel nuclides, characterized in that the evaluation and determination of whether the work is taken out. In the apparatus for separating nuclear fuel nuclides according to claim 13,
The holding device for holding the material for the purpose of identification, measurement and removal of the specific nuclide is a tip of an articulated arm inserted on the operation floor of the nuclear power plant or from the lateral outside of the containment vessel of the nuclear power plant And the material held by the holding device installed at the tip of the articulated arm is stored in the waste storage of the nuclear power generation facility,
The concentration or concentration ratio of the material stored in the waste storage is measured by the measuring device, and the concentration or concentration ratio of the material in the waste storage measured by the measuring device is set in advance What we want to evaluate based on the evaluation result by comparing and evaluating the target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide Whether it contains nuclear fuel, whether it contains alpha nuclide, whether it is treated as alpha waste, whether it is treated as general waste, whether it is treated as nuclear fuel material, whether it is treated as fuel debris Nuclear fuel and waste separation, nuclear fuel and waste separation, target nuclide and other classification of measurement control, and target nuclear species of safeguards and other separation and evaluation whether it is possible to separate and evaluate Radionuclide separation device. The nuclear fuel nuclides separating apparatus according to any one of claims 13 to 16,
The measuring device for measuring the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide is the entire inside of the reactor pressure vessel of the nuclear power plant, the containment vessel of the nuclear power plant It is installed in the whole inside, inside the nuclear building of the nuclear power plant, inside the waste storage of the nuclear power plant, whole area of the nuclear power plant and whole area outside the nuclear power plant, and the measurement The concentration or concentration ratio of the material (specific nuclide) measured by the device, and the target value of the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide preset are set as described above. Evaluated by comparing with an evaluation device, based on the evaluation result, what you want to evaluate is whether it contains nuclear fuel, whether it contains alpha nuclide, whether it is treated as alpha waste, handled as general waste Uka Whether or not it is handled as nuclear fuel material, whether or not it is handled as fuel debris, fuel debris and waste separation, nuclear fuel and waste separation, target for measurement control nuclides and other separation, safeguards target for Nuclear fuel nuclides separating apparatus characterized by judging whether it is possible to separate and evaluate. The nuclear fuel nuclides separating apparatus according to any one of claims 13 to 17, wherein
The measurement apparatus condenses the laser beam transmitted by the first optical fiber, and transmits the laser beam generated by the laser oscillator. The first optical fiber transmits the laser beam. A condensing optical system, and the laser light condensed by the condensing optical system is irradiated to a material for the purpose of identification, measurement and removal of the specific nuclide. At this time, identification, measurement and removal of the specific nuclide And a collection optical system for collecting light originating from the constituent radionuclide and material of the material for the purpose of identification, measurement and removal of the specific nuclide emitted from the surface of the material for the purpose, and the collection optical system A nuclear fuel nuclide sorting apparatus, comprising: a second optical fiber for transmitting the collected light to the evaluation device. The nuclear fuel nuclides separating apparatus according to any one of claims 13 to 17, wherein
The measurement apparatus comprises: a laser transmitter for generating a laser beam; an optical fiber for transmitting the laser beam generated from the laser transmitter; and a light collecting collector for collecting the laser beam transmitted by the optical fiber. An optical system and the laser beam collected by the collection and collection optical system are irradiated to the material for the purpose of identification, measurement and removal of the specific nuclide, and at this time identification, measurement and removal of the specific nuclide Light from the constituent nuclide and element of the material for the purpose of identification, measurement and removal of the specific nuclide emitted from the surface of the material for the purpose Nuclear fuel nuclides characterized in that the light collected by the collection optical system is reversely transmitted using the optical fiber, and the returned light is branched and transmitted to the evaluation device. Sorting device. The nuclear fuel nuclides separating apparatus according to any one of claims 13 to 17, wherein
The measurement apparatus condenses the laser beam transmitted by the first optical fiber, and transmits the laser beam generated by the laser oscillator. The first optical fiber transmits the laser beam. A collection and collection optical system, and the laser light collected by the collection and collection optical system is irradiated to a material for the purpose of identification, measurement and removal of the specific nuclide. At this time, identification of the specific nuclide An introduction pipe and a pump for introducing a product emitted from the surface of the material for the purpose of measurement and removal, a measurement cell into which the product is introduced through the introduction pipe and the pump, and a second laser beam A second laser transmitter for generating, a second optical fiber for transmitting the second laser light generated by the second laser transmitter, and the second laser transmitted by the second optical fiber The light is measured And a second light collecting and collecting optical system for collecting the second laser light from the second light collecting and collecting optical system to collect the second laser light from the second light collecting and collecting optical system. The component nuclide of the material for the purpose of identification, measurement and removal of the specific nuclide emitted from the product, light originating from the element is collected by the second condensing optical system and the second optical fiber And a beam splitter for splitting and transmitting the returned light to the evaluation device. The nuclear fuel nuclides separating apparatus according to any one of claims 13 to 17, wherein
The measuring device is provided at a rotary power machine generating a rotational force, a rotational force transmission shaft transmitting the rotational force from the rotational power machine, and an end of the rotational force transmission shaft, and identifies the specific nuclide by rotation. A core bit for crushing, decomposing, scraping material intended for measurement and removal, and the specific nuclide by the core bit,
Alternatively, a high pressure water jet pump generating high pressure water jet, a high pressure hose transmitting the high pressure water jet generated from the high pressure water jet pump, and a high pressure water jet nozzle collecting the high pressure water jet transmitted by the high pressure hose And injecting the high pressure water jet focused by the high pressure water jet nozzle onto the material for the purpose of identification, measurement and removal of the specific nuclide, wherein the purpose is identification, measurement and removal of the specific nuclide An introduction pipe and a pump for introducing a product generated by crushing, decomposition and scraping from materials, a measurement cell to which the product is introduced through the introduction pipe and the pump, a laser transmitter for generating a laser beam, Transmitting the laser beam generated by the laser transmitter A fiber, a collection and collection optical system for collecting the laser beam transmitted by the optical fiber onto the product in the measurement cell, and the laser light from the collection and collection optical system to the product By collecting the light, the component nuclide of the material for the purpose of identification, measurement, and removal of the specific nuclide emitted from the generation material, light due to the element is collected by the light collection and collection optical system A nuclear fuel nuclide sorting apparatus, comprising: a beam splitter that performs reverse transmission using the optical fiber and splits the returned light and transmits the branched light to the evaluation device. The apparatus for separating nuclear fuel nuclides according to any one of claims 13 to 21,
A material separating nuclear fuel nuclides characterized in that the material for identification, measurement and removal of the specific nuclides is covered with a shatterproof cover. The apparatus for separating nuclear fuel nuclides according to any one of claims 13 to 22,
ICP-MS (Inductive Plasma Mass Spectrometer), ICP-AES (Inductive Plasma Emission Spectrometric Analyzer) as a measuring device for measuring the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide Or XPS (X-ray electron spectroscopy), EDS (energy dispersive X-ray analysis), or WDS (wavelength dispersive X-ray analysis), or
Or a measuring device for measuring the concentration or concentration ratio of the material (specific nuclide) for the purpose of identification, measurement and removal of the specific nuclide and ICP-MS (inductive plasma mass spectrometer) or ICP-AES (inductive plasma emission spectroscopy) Analysis device), or XPS method (X-ray electron spectroscopy), or EDS method (energy dispersive X-ray analysis), or combination with WDS method (wavelength dispersive X-ray analysis), and various combinations thereof A nuclear fuel nuclide separating apparatus characterized by using The apparatus for separating nuclear fuel nuclides according to any one of claims 13 to 23,
Facilities using nuclear fuel include nuclear power generation facilities, dismantling facilities for nuclear power generation facilities, nuclear reactor decommissioning facilities, nuclear fuel manufacturing facilities, nuclear fuel handling facilities, nuclear fuel storage facilities, nuclear fuel reprocessing facilities, waste storage facilities, military facilities, The above facilities that caused the accident, nuclear power facilities that caused the accident, dismantling and decommissioning facilities of the accident furnace, fuel debris retrieval facilities, fuel debris investigation facilities, fuel debris sorting facilities, fuel debris storage facilities,
The nuclear fuel nuclide sorting apparatus, wherein the general nuclear facility is a nuclear power generation facility, a dismantling facility for a nuclear power generation facility, a decommissioning facility for nuclear reactors, and a waste storage facility.

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