An analytical laboratory system for a spent fuel reprocessing plant

Abstract

The present invention provides a spent fuel reprocessing plant analysis laboratory system, including: an online analysis system, a pneumatic sample delivery system, and high-radiation, medium-radiation, product, and low-radiation analysis systems in a laboratory platform, as well as a laboratory control system and a three-waste management system. The online analysis system is used to perform online analysis on samples in a post-processing process plant. The pneumatic sample delivery system is connected between each post-processing process plant and the laboratory platform, and is used to distribute the samples in the post-processing process plant to the corresponding analysis system of the laboratory platform according to the sample analysis task, so that each analysis system can complete the corresponding analysis task. The present invention starts from the actual analysis needs of the post-processing plant, and by designing a complete and reasonable system architecture, while ensuring sample analysis, it takes into account the supporting conditions such as sample transmission, quality control, and three-waste management, thereby ensuring the normal, stable, and safe operation of the analysis laboratory of the post-processing plant.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear fuel post-processing, and in particular to an analytical laboratory system for a spent fuel post-processing plant. Background Art

[0002] The analysis laboratory of the reprocessing plant is the "eye" of the main reprocessing process and the three waste treatment process, and is a key sub-project to ensure the safe and stable operation of the reprocessing process. The task of this laboratory is to provide timely and reliable analysis results and timely feedback for all main processes and three waste treatment processes, meet the requirements of process control, nuclear material balance, product inspection, criticality safety control, etc., so as to ensure the safe, stable and effective operation of the process and obtain qualified uranium and plutonium products. Due to the complex sources of the analysis samples of the reprocessing plant, the large sample scale, the diversity of analysis items, the large number and variety of analysis instruments, the cumbersome sample circulation, and the certain radioactivity of the samples, there are particularities in the design of analysis principles, analysis operations and analysis methods. At the same time, there is a lack of a systematic concept of the analysis laboratory of the reprocessing plant. For example, the Chinese invention patent application CN112630455A discloses a method and system for the analysis of spent fuel reprocessing plant samples, which mainly focuses on the sample analysis process and does not comprehensively plan the overall design of the analysis laboratory of the reprocessing plant. In addition, the design methods of ordinary laboratories at home and abroad are far from meeting the analysis needs of the analysis laboratory of the reprocessing plant.

[0003] The design of analytical laboratories in traditional post-processing plants in my country has at least the following deficiencies:

[0004] (1) The design concept could not be comprehensively planned according to the particularity of the analytical laboratory of the post-processing plant. Instead, some laboratory rooms were designed and some chambers were arranged in the rooms. The process analysis requirements were not clearly defined, and some analytical items did not have corresponding analytical methods.

[0005] (2) For high-level samples and positions where sample analysis is difficult, no automatic analysis method is set up, and non-automatic analysis is time-consuming and inefficient;

[0006] (3) Some small instruments are sealed in a glove box, which is inconvenient for personnel to operate. The electronic components of the instruments are easily damaged by radiation, affecting the performance of the instruments.

[0007] (4) The waste liquid, solid waste and waste gas generated during the analysis process were not properly handled, and the overall analysis process lacked quality control measures. Summary of the invention

[0008] The technical problem to be solved by the present invention is to provide a spent fuel reprocessing plant analysis laboratory system in view of the above-mentioned deficiencies in the prior art, so as to solve the problems existing in the system design of the traditional reprocessing plant analysis laboratory.

[0009] The technical solution adopted to solve the technical problem of the present invention is:

[0010] The present invention provides a spent fuel reprocessing plant analysis laboratory system, comprising:

[0011] Online analysis system, pneumatic sample delivery system and laboratory platform, the laboratory platform includes high-radiation analysis system, medium-radiation analysis system, product analysis system, low-radiation analysis system, laboratory control system and three-waste management system,

[0012] The online analysis system includes an online analysis instrument arranged in each post-processing process plant, which is used to perform online analysis on samples in the corresponding post-processing process plant to complete the online sample analysis task;

[0013] The pneumatic sample delivery system is connected between each post-processing process plant and the laboratory platform, and is used to distribute the samples in the post-processing process plant to the corresponding analysis system of the laboratory platform according to the sample analysis task.

[0014] The high-level analysis system is used to receive the high-level samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the high-level samples;

[0015] The medium-pressure analysis system is used to receive the medium-pressure samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the medium-pressure samples;

[0016] The low-level analysis system is used to receive the low-level samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the low-level samples;

[0017] The product analysis system is used to receive the radioactive element samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the radioactive element samples;

[0018] The laboratory control system is electrically connected to the analytical instruments in the online analysis system, the high-radiation analysis system, the medium-radiation analysis system, the product analysis system and the low-radiation analysis system, respectively, and is used to receive the experimental results of the analytical instruments in each analysis system and upload them to the control center, and store and manage the standard substances, gas cylinders and analytical reagents required by the laboratory system;

[0019] The three waste management systems are respectively connected to the high-radiation analysis system, the medium-radiation analysis system, the low-radiation analysis system and the product analysis system, and are used to receive and process waste generated by analyzing samples in each analysis system.

[0020] Optionally, the high-radiation analysis system includes a high-radiation automatic analysis unit, a high-radiation process analysis unit and a high-radiation waste liquid analysis unit.

[0021] The pneumatic sample delivery system is used to transfer the high-level radioactive samples in the post-processing process plant to the high-level radioactive automatic analysis unit for automatic high-level radioactive non-destructive analysis, and after the high-level radioactive automatic analysis is completed or when the high-level radioactive automatic analysis unit is unable to analyze, the high-level radioactive samples are transferred to the high-level radioactive process analysis unit or the high-level radioactive waste liquid analysis unit according to their source and analysis items.

[0022] The high-level radioactive process analysis unit is used to analyze the high-level radioactive process samples transmitted by the pneumatic sample delivery system, and the high-level radioactive liquid waste analysis unit is used to analyze the high-level radioactive waste samples transmitted by the pneumatic sample delivery system.

[0023] Optionally, the high-radiation automatic analysis unit includes an analysis room and multiple sets of automatic analyzers arranged in the analysis room. A high-radiation automatic analysis post is provided in the analysis room. The pneumatic sample delivery system is used to transfer the high-radiation samples in the post-processing process building to the high-radiation automatic analysis post. The automatic analyzer is used to automatically perform corresponding non-destructive analysis on the high-radiation samples at the high-radiation automatic analysis post.

[0024] Optionally, the high-radiation process analysis unit includes a balance analysis shielding room and a high-radiation process analysis hot room, the balance analysis shielding room is provided with a balance analysis device, and the high-radiation process analysis hot room is divided into a first automatic transfer area and a first manual analysis area by a partition.

[0025] The pneumatic sample delivery system is used to transfer the high-radiation process samples in the post-processing process building to the first automatic transfer area for temporary storage, and is also used to transfer the high-radiation process samples temporarily stored in the first automatic transfer area to the high-radiation automatic analysis position, and is also used to transfer the high-radiation process samples to the first automatic transfer area for temporary storage after the high-radiation automatic analysis is completed or when the high-radiation automatic analysis unit is unable to analyze, and is also used to manually move the high-radiation process samples temporarily stored in the first automatic transfer area to the first manual analysis area for acid analysis or pretreatment, and then transfer the high-radiation process samples after acid analysis to the balance analysis shielding room, and transfer the high-radiation process samples after pretreatment to the medium-radiation analysis system or the low-radiation analysis system; the balance analysis equipment is used to perform balance analysis on the high-radiation process samples in the balance analysis shielding room.

[0026] Optionally, the high-level waste liquid analysis unit comprises a multi-element analysis shielding room and a high-level waste liquid analysis hot room, wherein the multi-element analysis shielding room is provided with anion and cation analysis equipment, and the high-level waste liquid analysis hot room is divided into a second automatic transfer area and a second manual analysis area by a partition.

[0027] The pneumatic sample delivery system is used to transfer the high-level radioactive waste samples in the post-processing process plant to the second automatic transfer area for temporary storage, and is also used to transfer the high-level radioactive waste samples temporarily stored in the second automatic transfer area to the high-level automatic analysis position, and is also used to transfer the high-level radioactive waste samples to the second automatic transfer area for temporary storage after the high-level automatic analysis is completed or when the high-level automatic analysis unit cannot perform analysis, and is also used to manually move the high-level radioactive waste samples temporarily stored in the second automatic transfer area to the second manual analysis area for acid analysis, salt content analysis or pretreatment, and then transfer the high-level radioactive waste samples after acid analysis or salt content analysis to the multi-element analysis shielding room, and transfer the pretreated high-level radioactive waste samples to the medium-level analysis system or the low-level analysis system; the anion and cation analysis equipment is used to perform anion and cation analysis on the high-level radioactive waste samples in the multi-element analysis shielding room.

[0028] Optionally, the intermediate-level radioactive analysis system includes an intermediate-level radioactive automatic analysis unit, an intermediate-level radioactive process analysis unit, an intermediate-level radioactive three wastes analysis unit and an isotope analysis unit.

[0029] The pneumatic sample delivery system is used to transfer the intermediate-level radioactive samples in the post-processing process building or the intermediate-level radioactive samples formed by pre-processing the high-level radioactive samples by the high-level radioactive analysis system to the intermediate-level radioactive automatic analysis unit, so as to automatically perform intermediate-level radioactive non-destructive analysis, and after the intermediate-level radioactive automatic analysis is completed or when the intermediate-level radioactive automatic analysis unit cannot perform analysis, the intermediate-level radioactive samples are transferred to the intermediate-level radioactive process analysis unit or the intermediate-level three-waste analysis unit according to their sources and analysis items.

[0030] The medium-level radioactive process analysis unit is used to analyze the medium-level radioactive process samples transmitted by the pneumatic sample delivery system. The medium-level radioactive waste analysis unit is used to analyze the medium-level radioactive waste samples transmitted by the pneumatic sample delivery system.

[0031] The pneumatic sample delivery system is also used to transmit the intermediate-level radioactive process sample to the isotope analysis unit for isotope analysis after the intermediate-level radioactive process sample is analyzed by the intermediate-level radioactive process analysis unit.

[0032] Optionally, the medium-level process analysis unit includes at least one medium-level process glove box analysis line,

[0033] The medium-release process glove box analysis line includes a plurality of process glove boxes connected in sequence, the plurality of process glove boxes including a process sample receiving and sending glove box, a process sample pretreatment glove box and at least one process sample analysis glove box, wherein the process sample analysis glove box is provided with a process sample analysis instrument.

[0034] The pneumatic sample delivery system is used to transfer the intermediate-radiation process samples in the post-processing process building or the intermediate-radiation process samples whose radioactivity is reduced to the intermediate-radiation level by pre-processing the high-radiation process samples by the high-radiation analysis system to the process sample sending and receiving glove box for temporary storage, and is also used to transfer the intermediate-radiation process samples temporarily stored in the process sample sending and receiving glove box to the intermediate-radiation automatic analysis unit to automatically perform intermediate-radiation non-destructive analysis, and after the intermediate-radiation automatic analysis is completed or when the intermediate-radiation automatic analysis unit cannot perform analysis, transfer the intermediate-radiation process samples to the process sample sending and receiving glove box for manual processing to complete the intermediate-radiation automatic analysis or the intermediate-radiation automatic analysis unit in the process sample sending and receiving glove box. When the intermediate-level radioactivity process samples that cannot be analyzed are moved to the process sample analysis glove box for analysis and then moved back to the process sample sending and receiving glove box, the pneumatic sample delivery system is used to transfer the intermediate-level radioactivity process samples that have completed the analysis to the isotope analysis unit for isotope analysis; or when the intermediate-level radioactivity process samples that have completed the intermediate-level radioactivity automatic analysis in the process sample sending and receiving glove box or that cannot be analyzed by the intermediate-level radioactivity automatic analysis unit are manually moved to the process sample pretreatment glove box for pretreatment and then moved back to the process sample sending and receiving glove box, the pneumatic sample delivery system is used to transfer the low-level process samples that have completed the pretreatment and whose radioactivity activity has been reduced to a low-level level to the low-level analysis system.

[0035] Optionally, the intermediate-level three-waste analysis unit comprises at least one intermediate-level three-waste glove box analysis line,

[0036] The medium-level three-waste glove box analysis line includes a plurality of three-waste glove boxes connected in sequence, the plurality of three-waste glove boxes include a three-waste sample receiving and sending glove box, a three-waste sample pretreatment glove box and at least one three-waste sample analysis glove box, and the three-waste sample analysis glove box is provided with a three-waste sample analysis instrument.

[0037] The pneumatic sample delivery system is used to transfer the intermediate-level radioactive waste samples in the post-processing process plant or the intermediate-level radioactive waste samples formed by pre-processing the high-level radioactive waste samples by the high-level radioactive analysis system to the intermediate-level radioactive waste sample sending and receiving glove box for temporary storage, and is also used to transfer the intermediate-level radioactive waste samples temporarily stored in the three-waste sample sending and receiving glove box to the intermediate-level radioactive waste automatic analysis unit to automatically perform intermediate-level radioactive non-destructive analysis, and after the intermediate-level radioactive waste automatic analysis is completed or when the intermediate-level radioactive waste automatic analysis unit cannot perform analysis, the intermediate-level radioactive waste samples are transferred to the three-waste sample sending and receiving glove box, and the intermediate-level radioactive waste samples in the three-waste sample sending and receiving glove box that have completed the intermediate-level radioactive waste automatic analysis or cannot be analyzed by the intermediate-level radioactive waste automatic analysis unit are manually moved to the three-waste sample analysis glove box for analysis,

[0038] When the intermediate-level radioactive waste samples that have completed the intermediate-level radioactive automatic analysis in the process sample sending and receiving glove box or cannot be analyzed by the intermediate-level radioactive automatic analysis unit are manually moved to the three-waste sample pretreatment glove box to complete the pretreatment and then moved back to the three-waste sample sending and receiving glove box, the pneumatic sample delivery system is used to transmit the low-level radioactive waste samples that have completed the pretreatment and whose radioactive activity has been reduced to a low-level level to the low-level analysis system.

[0039] Optionally, the low-radiation analysis system includes a radioactive source and measurement unit, a mass spectrometry unit and other low-radiation analysis units.

[0040] The radioactive source and measurement unit is used to measure the radioactivity or nuclide of low-level samples.

[0041] The mass spectrometry unit is used for the analysis of trace or ultra-trace uranium, neptunium and plutonium and other impurity elements.

[0042] The other low-level analysis units are used for routine analysis of low-level samples.

[0043] Optionally, the product analysis system includes a plutonium product analysis unit and a uranium product analysis unit,

[0044] The plutonium product analysis unit includes a plutonium product powder glove box analysis line and a plutonium product coulometric glove box analysis line. The plutonium product powder glove box analysis line is used to perform physical property analysis and non-metallic impurity analysis on plutonium powder, and the plutonium product coulometric analysis line is used to perform dissolution and precise analysis on plutonium powder and filter cake.

[0045] The uranium product analysis unit includes a uranium product powder glove box analysis line and a uranium product potentiometric titration glove box analysis line. The uranium product powder glove box analysis line is used to perform physical property analysis and non-metallic impurity analysis on uranium powder, and the uranium product potentiometric titration glove box analysis line is used to perform dissolution, pretreatment separation and precise uranium content analysis on uranium powder.

[0046] Optionally, the laboratory control system includes a standard substance management unit, an analytical laboratory information management unit, and an analytical reagent and gas cylinder management unit.

[0047] The analytical laboratory information management unit is electrically connected to the analytical instruments in the online analysis system, the high-radiation analysis system, the medium-radiation analysis system, the product analysis system and the low-radiation analysis system, respectively, and is used to receive the experimental results of the analytical instruments in each analysis system and upload them to the control center.

[0048] The standard substance management unit is used to store and manage special standard substances in the nuclear field and conventional standard substances in analytical chemistry.

[0049] The analytical reagent and gas cylinder management unit is used for storing and managing gas cylinders and analytical reagents of a laboratory platform.

[0050] Optionally, the three waste management system includes a solid waste management unit and a radioactive waste liquid and storage tank exhaust gas treatment unit.

[0051] The solid waste management unit is used to uniformly collect and process the solid waste generated by the laboratory platform.

[0052] The radioactive waste liquid and storage tank exhaust gas treatment unit is connected to the online analysis system, high-level analysis system, medium-level analysis system, product analysis system and low-level analysis system through pipelines. It is used to collect the waste liquid generated by each analysis system into storage tanks according to their types and discharge them uniformly, and at the same time merge the exhaust gases generated by different storage tanks and discharge them uniformly to the exhaust gas main pipe.

[0053] The present invention starts from the actual analysis needs of the post-processing plant and designs a complete and reasonable system architecture. While ensuring sample analysis, it also takes into account supporting conditions such as sample transmission, quality control and three wastes management, thereby solving the problems of cumbersome sample flow paths, low efficiency of non-automatic analysis, backward sealing methods of analysis equipment, lack of quality control of the analysis process, etc., and ensures the normal, stable and safe operation of the analysis laboratory of the post-processing plant. BRIEF DESCRIPTION OF THE DRAWINGS

[0054] Figure 1 The overall architecture diagram of the spent fuel reprocessing plant analysis laboratory system provided in Example 1 of the present invention;

[0055] Among them, 1-online analysis system; 2-pneumatic sample delivery system; 3-high-level analysis system; 4-medium-level analysis system; 5-product analysis system; 6-low-level analysis system; 7-laboratory quality assurance and quality control system; 8-three wastes management system; 9-first sub-item online analysis unit; 10-second sub-item online analysis unit; 11-high-level automatic analysis unit; 12-high-level process analysis unit; 13-high-level liquid waste analysis unit; 14-medium-level automatic analysis unit; 15-medium-level process analysis unit; 16-medium-level three wastes analysis unit; 17-isotope analysis unit; 18-plutonium product analysis unit; 19-uranium product analysis unit; 20-radioactive source preparation and measurement unit; 21-mass spectrometry analysis unit; 22-other low-level analysis units; 23-standard material management unit; 24-analysis laboratory information management unit; 25-analysis reagent and gas cylinder management unit; 26-solid waste management unit; 27-radioactive liquid waste and storage tank exhaust gas treatment unit;

[0056] Figure 2 This is a schematic diagram of sample flow in a high-level analysis system of an analysis laboratory in a spent fuel reprocessing plant according to an embodiment of the present invention;

[0057] Among them, 28-high-level process samples; 29-high-level three waste samples; 30-balance analysis shielded room; 31-high-level process analysis hot room; 32-high-level waste liquid analysis hot room; 33-multi-element analysis shielded room; 34-first automatic transfer area; 35-first manual analysis area; 36-second manual analysis area; 37-second automatic transfer area; 38-high-level automatic analysis position;

[0058] Figure 3This is a schematic diagram of sample flow in the radioactive analysis system of the spent fuel reprocessing plant analysis laboratory according to an embodiment of the present invention;

[0059] Among them, 39-medium-level radioactive process samples; 40-medium-level radioactive three waste samples; 41-low-level radioactive samples; 42-first medium-level radioactive process analysis line; 43-second medium-level radioactive process analysis line; 44-medium-level radioactive automatic analysis station; 45-medium-level radioactive three waste analysis line.

[0060] Figure 4 It is a schematic diagram of the analysis line and modular design of the analysis laboratory of the spent fuel reprocessing plant according to an embodiment of the present invention. DETAILED DESCRIPTION

[0061] The following will be combined with the accompanying drawings in the present invention to clearly and completely describe the technical solutions in the invention. Obviously, the described embodiments are part of the embodiments of the present invention, rather than all the embodiments. Based on the embodiments in the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of the present invention.

[0062] In the description of the present invention, it should be noted that the directions or positional relationships indicated by “upper” and the like are based on the directions or positional relationships shown in the accompanying drawings and are only for the convenience and simplification of the description. They do not indicate or imply that the device or element referred to must have a specific direction, be constructed and operated in a specific direction. Therefore, they cannot be understood as limitations on the present invention.

[0063] In the description of the present invention, the terms “first” and “second” are used for descriptive purposes only and should not be understood as indicating or implying relative importance.

[0064] In the description of the present invention, it should be noted that, unless otherwise clearly specified and limited, the terms "connect", "set", "install", "fix" and the like should be understood in a broad sense, for example, it can be a fixed connection or a detachable connection, or an integral connection; it can be a direct connection or an indirect connection through an intermediate medium, or it can be the internal communication of two components. For those skilled in the art, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[0065] The present invention provides a spent fuel reprocessing plant analysis laboratory system, comprising:

[0066] Online analysis system, pneumatic sample delivery system and laboratory platform, the laboratory platform includes high-radiation analysis system, medium-radiation analysis system, product analysis system, low-radiation analysis system, laboratory control system and three-waste management system,

[0067] The online analysis system includes an online analysis instrument arranged in each post-processing process plant, which is used to perform online analysis on samples in the corresponding post-processing process plant to complete the online sample analysis task;

[0068] The pneumatic sample delivery system is connected between each post-processing process plant and the laboratory platform, and is used to distribute the samples in the post-processing process plant to the corresponding analysis system of the laboratory platform according to the sample analysis task.

[0069] The high-level analysis system is used to receive the high-level samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the high-level samples;

[0070] The medium-pressure analysis system is used to receive the medium-pressure samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the medium-pressure samples;

[0071] The low-level analysis system is used to receive the low-level samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the low-level samples;

[0072] The product analysis system is used to receive the radioactive element samples distributed by the pneumatic sample delivery system and analyze the samples to complete the analysis task of the radioactive element samples;

[0073] The laboratory control system is electrically connected to the analytical instruments in the online analysis system, the high-radiation analysis system, the medium-radiation analysis system, the product analysis system and the low-radiation analysis system, respectively, and is used to receive the experimental results of the analytical instruments in each analysis system and upload them to the control center, and store and manage the standard substances, gas cylinders and analytical reagents required by the laboratory system;

[0074] The three waste management systems are respectively connected to the high-radiation analysis system, the medium-radiation analysis system, the low-radiation analysis system and the product analysis system, and are used to receive and process waste generated by analyzing samples in each analysis system.

[0075] Embodiment 1:

[0076] like Figure 1 As shown, this embodiment provides a spent fuel reprocessing plant analysis laboratory system, including:

[0077] Online analysis system 1, pneumatic sample delivery system 2 and laboratory platform. The laboratory platform includes high-radiation analysis system 3, medium-radiation analysis system 4, product analysis system 5, low-radiation analysis system 6, laboratory control system 7 and three-waste management system 8.

[0078] The online analysis system 1 includes online analysis instruments arranged in each post-processing process plant, and is used to perform online analysis on samples in the corresponding post-processing process plant to complete the online sample analysis task;

[0079] The pneumatic sample delivery system 2 is connected between each post-processing workshop and the laboratory platform, and is used to distribute the samples in the post-processing workshop to the corresponding analysis system of the laboratory platform according to the sample analysis task.

[0080] The high-level analysis system 3 is used to receive the high-level samples distributed by the pneumatic sample delivery system 2 and analyze the samples to complete the analysis task of the high-level samples;

[0081] The medium-pressure analysis system 4 is used to receive the medium-pressure samples distributed by the pneumatic sample delivery system 2 and analyze the samples to complete the analysis task of the medium-pressure samples;

[0082] The low-level analysis system 4 is used to receive the low-level samples distributed by the pneumatic sample delivery system 2 and analyze the samples to complete the analysis task of the low-level samples;

[0083] The product analysis system 5 is used to receive the radioactive element samples distributed by the pneumatic sample delivery system 2 and analyze the samples to complete the analysis task of the radioactive element samples;

[0084] The laboratory control system 7 is electrically connected to the analytical instruments in the online analysis system 1, the high-radiation analysis system 3, the medium-radiation analysis system 4, the product analysis system 5 and the low-radiation analysis system 6, respectively, for receiving the experimental results of the analytical instruments in each analysis system and uploading them to the control center, and storing and managing the standard substances, gas cylinders and analytical reagents required by the laboratory system;

[0085] The three waste management system 8 is connected to the high-radiation analysis system 3, the medium-radiation analysis system 4, the low-radiation analysis system 4 and the product analysis system 5 respectively, and is used to receive and process the waste generated by the analysis of samples by each analysis system.

[0086] The present invention starts from the actual analysis needs of the post-processing plant and designs a complete and reasonable system architecture. While ensuring sample analysis, it also takes into account supporting conditions such as sample transmission, quality control and three wastes management, thereby solving the problems of cumbersome sample flow paths, low efficiency of non-automatic analysis, backward sealing methods of analysis equipment, lack of quality control of the analysis process, etc., and ensures the normal, stable and safe operation of the analysis laboratory of the post-processing plant.

[0087] In this embodiment, after building the above system architecture of the analytical laboratory system, different functional units are respectively set in the analytical system, and chambers and analytical instruments are directly set in some functional units; or analytical lines are set in some functional units, and chambers and analytical instruments are set in the analytical lines, and then the analytical chambers and analytical instruments are modularized or chamber-integrated according to the analysis requirements. The specific layout is as follows:

[0088] In this embodiment, the online analysis system 1 includes a first sub-item online analysis unit 9 and a second sub-item online analysis unit 10, which are respectively arranged in the first sub-item plant and the second sub-item plant. Three online process analysis points are set in the first sub-item online analysis unit 9, which are the online analysis of uranium and gamma in the 1# process point, the online analysis of plutonium in the 2# process point, and the online analysis of plutonium in the 3# process point. The analysis of uranium in the 1# process point adopts the gamma absorption method, and the online analysis of total gamma in the 1# process point adopts the NaI gamma spectrometry; the online analysis of plutonium in the 2# process point and the 3# process point both adopts the energy dispersive X-ray fluorescence method. Two online process analysis points are set in the second sub-item online analysis unit 10, which are the analysis of uranium in the 4# process point and the analysis of uranium in the 5# process point, and the analysis of uranium both adopts the gamma absorption method.

[0089] In this embodiment, the analytical instruments used in the above-mentioned online analysis system are all designed to be integrated with the glove box. The process liquid flow is lifted by air to the measurement flow cell in the online analysis glove box, and then returns to the process liquid flow. The excitation source and detector of the online analytical instrument are inserted into the glove box from the outside through the sleeve, and are effectively matched with the flow cell in the glove box. When calibrating and maintaining the instrument, the excitation source and detector can be pulled out of the sleeve respectively for calibration and maintenance; or online calibration can be achieved by adding a turntable structure in the glove box.

[0090] The pneumatic sample delivery system 2 delivers the radioactive liquid samples or neptunium and plutonium products that need to be analyzed in each process plant to the analysis laboratory by pneumatic transmission, and realizes the sample transmission between the analysis lines inside the analysis laboratory.

[0091] In this embodiment, the high-radiation analysis system 3 includes a high-radiation automatic analysis unit 11, a high-radiation process analysis unit 12 and a high-radiation waste liquid analysis unit 13.

[0092] The pneumatic sample delivery system 2 is used to transfer the high-level radioactive samples in the post-processing plant to the high-level radioactive automatic analysis unit 11 for automatic high-level radioactive non-destructive analysis. After the high-level radioactive automatic analysis is completed or when the high-level radioactive automatic analysis unit 11 is unable to perform analysis, the high-level radioactive samples are transferred to the high-level radioactive process analysis unit 12 or the high-level radioactive waste liquid analysis unit 13 according to their source and analysis items.

[0093] The high-level radioactive process analysis unit 12 is used to analyze the high-level radioactive process samples transmitted by the pneumatic sample delivery system 2 , and the high-level radioactive waste liquid analysis unit 13 is used to analyze the high-level radioactive waste samples transmitted by the pneumatic sample delivery system 2 .

[0094] In this embodiment, the high-radiation automatic analysis unit 11 includes an analysis room and multiple sets of automatic analyzers installed in the analysis room. A high-radiation automatic analysis post 38 is provided in the analysis room. The pneumatic sample delivery system 2 is used to transfer the high-radiation samples in the post-processing process plant to the high-radiation automatic analysis post 38. The automatic analyzer is used to automatically perform corresponding non-destructive analysis on the high-radiation samples on the high-radiation automatic analysis post 38.

[0095] In this embodiment, the high-radiation process analysis unit 12 includes a balance analysis shielding room 30 and a high-radiation process analysis hot room 31. The balance analysis shielding room 30 is provided with a balance analysis device. The high-radiation process analysis hot room 31 is divided into a first automatic transfer area 34 and a first manual analysis area 35 by a partition.

[0096] The pneumatic sample delivery system 2 is used to transfer the high-radiation process samples in the post-processing process plant to the first automatic transfer area 34 for temporary storage, and is also used to transfer the high-radiation process samples temporarily stored in the first automatic transfer area 34 to the high-radiation automatic analysis position 38. It is also used to transfer the high-radiation process samples to the first automatic transfer area 34 for temporary storage after the high-radiation automatic analysis is completed or when the high-radiation automatic analysis unit 11 cannot perform the analysis. It is also used to manually move the high-radiation process samples temporarily stored in the first automatic transfer area 34 to the first manual analysis area 35 for acid analysis or pretreatment, and then transfer the high-radiation process samples after acid analysis to the balance analysis shielding room 30, and transfer the high-radiation process samples after pretreatment to the medium-radiation analysis system 4 or the low-radiation analysis system 6; the balance analysis equipment is used to perform balance analysis on the high-radiation process samples in the balance analysis shielding room 30.

[0097] In this embodiment, the high-level waste liquid analysis unit 13 includes a multi-element analysis shielding room 33 and a high-level waste liquid analysis hot room 32. The multi-element analysis shielding room 33 is provided with anion and cation analysis equipment. The high-level waste liquid analysis hot room 32 is divided into a second automatic transfer area 37 and a second manual analysis area 36 by a partition.

[0098] The pneumatic sample delivery system 2 is used to transfer the high-level radioactive waste samples in the post-processing process plant to the second automatic transfer area 37 for temporary storage, and is also used to transfer the high-level radioactive waste samples temporarily stored in the second automatic transfer area 37 to the high-level automatic analysis position 38. It is also used to transfer the high-level radioactive waste samples to the second automatic transfer area 37 for temporary storage after the high-level automatic analysis is completed or when the high-level automatic analysis unit 11 cannot perform the analysis. It is also used to manually move the high-level radioactive waste samples temporarily stored in the second automatic transfer area 37 to the second manual analysis area 36 for acid analysis, salt content analysis or pretreatment, and then transfer the high-level radioactive waste samples after acid analysis or salt content analysis to the multi-element analysis shielded room 33, and transfer the pretreated high-level radioactive waste samples to the medium-level analysis system 4 or the low-level analysis system 6; the anion and cation analysis equipment is used to perform anion and cation analysis on the high-level radioactive waste samples in the multi-element analysis shielded room 33.

[0099] In summary, high-level radioactive samples are preferentially transmitted to the high-level radioactive automatic analysis unit 11 for automatic analysis through the pneumatic sample delivery system 2. High-level radioactive samples that cannot be automatically analyzed are sent to the high-level radioactive process analysis unit 12 and the high-level radioactive waste liquid analysis unit 13 for analysis through the pneumatic sample delivery system 2 according to their sources and analysis items.

[0100] Among them, high-level samples include high-level process samples 28 and high-level waste samples 29. High-level process samples 28 come from the main process flow of post-processing with a radioactivity level greater than or equal to n×10 9 Bq / L (n<10); high-level three-waste sample 29 comes from the radioactivity level greater than or equal to n×10 in the three-waste post-processing process 9 Bq / L (n<10) samples.

[0101] The automatic analyzers in the analysis room of the high-level radioactive automatic analysis unit 11 include one or more analysis equipment such as an automatic hybrid KED / XRF analyzer, an automatic graphite crystal pre-diffraction X-ray fluorescence analyzer, and an automatic high-purity germanium gamma spectrometer. The sample is directly sent to the high-level radioactive automatic analysis station 38 through the pneumatic sample delivery system 2, and the sample bottle is directly analyzed non-destructively without opening the cover. After the analysis is completed, the sample is returned to the high-level radioactive process analysis hot cell 31 or the high-level radioactive waste liquid analysis hot cell 32 through the pneumatic sample delivery system 2.

[0102] The high-radiation process analysis unit 12 is provided with a high-radiation process analysis hot chamber 31 and a balance analysis shielding chamber 30. The high-radiation process samples 28 that cannot be automatically analyzed in the post-processing process sub-items and the high-radiation process samples 28 automatically analyzed and returned by the high-radiation automatic analysis post 38 are all analyzed in the high-radiation process analysis unit 12.

[0103] In this embodiment, the high-radiation process analysis hot chamber 31 is divided into a first automatic transfer area 34 and a first manual analysis area 35 by a partition. The partition is made of stainless steel or carbon steel. A sample transfer door is set on the hot chamber partition for transferring samples between the two areas. The first automatic transfer area 34 is used for temporary storage and transfer of high-radiation process samples 28 before they are sent to the high-radiation automatic analysis station 38; the first manual analysis area 35 receives samples that cannot be automatically analyzed and performs sample analysis operations.

[0104] The high-level radioactive liquid waste analysis unit 13 is equipped with a high-level radioactive liquid waste analysis hot chamber 32 and a multi-element analysis shielding chamber 33. The high-level radioactive waste samples 29 that cannot be automatically analyzed in the post-processing three wastes sub-item and the high-level radioactive waste samples 29 returned by automatic analysis at the high-level automatic analysis post 38 are all analyzed in the high-level radioactive liquid waste analysis unit 13.

[0105] In this embodiment, the high-level waste liquid analysis hot room 32 is divided into a second automatic transfer area 37 and a second manual analysis area 36 by a partition, and the partition is also made of stainless steel or carbon steel. A sample transfer door is set on the hot room partition for transferring samples between the two areas. The second automatic transfer area 37 is used for temporary storage and transfer of high-level waste samples 29 before they are sent to the high-level automatic analysis station 38; the second manual analysis area 36 receives samples that cannot be automatically analyzed and performs sample analysis operations.

[0106] like Figure 2 The figure shows a schematic diagram of sample flow in the high-radiation analysis system. The high-radiation process samples 28 obtained from the post-processing plant are preferentially sent to the high-radiation process analysis hot chamber 31 of the analysis laboratory through the pneumatic sample delivery system 2. Among them, the samples that need to be automatically analyzed are directly sent to the first automatic transfer area 34 for temporary storage or transfer, and then transmitted to the high-radiation automatic analysis position 38 in the high-radiation automatic analysis unit 11 through the pneumatic sample delivery system 2 for automatic analysis. The samples that cannot be automatically analyzed are sent to the first manual analysis area 35 for acidity analysis, and the pre-treated or sampled samples are sent to the shielding chamber 30 for balance analysis in the process liquid. The high-level radioactive waste samples 29 obtained from the post-processing waste plant are preferentially sent to the high-level radioactive waste liquid analysis hot cell 32 of the analysis laboratory through the pneumatic sample delivery system 2. Among them, the samples that need to be automatically analyzed are directly sent to the second automatic transfer area 37 for temporary storage or transfer, and then transmitted to the high-level radioactive waste automatic analysis position 38 in the high-level radioactive waste automatic analysis unit 11 through the pneumatic sample delivery system 2 for automatic analysis. The samples that cannot be automatically analyzed are sent to the second manual analysis area 36 for acidity analysis, salt content analysis, pretreatment or sample separation to the multi-element analysis shielding chamber 33 for analysis of anions and cations in the high-level radioactive waste liquid.

[0107] In this embodiment, the medium-level radioactive analysis system 4 includes a medium-level radioactive automatic analysis unit 14, a medium-level radioactive process analysis unit 15, a medium-level radioactive three wastes analysis unit 16 and an isotope analysis unit 17.

[0108] The pneumatic sample delivery system 2 is used to transfer the intermediate-level radioactive samples in the post-processing process building or the intermediate-level radioactive samples whose radioactivity is reduced to the intermediate-level radioactive level by pre-processing the high-level radioactive samples by the high-level radioactive analysis system 3 to the intermediate-level radioactive automatic analysis unit 14, so as to automatically perform intermediate-level radioactive non-destructive analysis. After the intermediate-level radioactive automatic analysis is completed or when the intermediate-level radioactive automatic analysis unit 14 cannot perform analysis, the intermediate-level radioactive samples are transferred to the intermediate-level radioactive process analysis unit 15 or the intermediate-level three-waste analysis unit 16 according to their sources and analysis items.

[0109] The intermediate-level radioactive process analysis unit 15 is used to analyze the intermediate-level radioactive process samples transmitted by the pneumatic sample delivery system 2, and the intermediate-level radioactive three wastes analysis unit 16 is used to analyze the intermediate-level radioactive three wastes samples transmitted by the pneumatic sample delivery system 2.

[0110] The pneumatic sample delivery system 2 is also used to transmit the intermediate-level radioactive process sample to the isotope analysis unit 17 for isotope analysis after the intermediate-level radioactive process sample is analyzed by the intermediate-level radioactive process analysis unit 15 .

[0111] In this embodiment, the medium-level process analysis unit 15 includes at least one medium-level process glove box analysis line.

[0112] The medium-level process glove box analysis line includes a plurality of process glove boxes connected in sequence, wherein the plurality of process glove boxes include a process sample receiving and sending glove box, a process sample pretreatment glove box and at least one process sample analysis glove box, and the process sample analysis glove box is provided with a process sample analysis instrument.

[0113] The pneumatic sample delivery system 2 is used to transfer the medium-radioactive process samples in the post-processing process building or the medium-radioactive process samples formed by pre-processing the high-radioactive process samples by the high-radioactive analysis system 3 to the process sample sending and receiving glove box for temporary storage, and is also used to transfer the medium-radioactive process samples temporarily stored in the process sample sending and receiving glove box to the medium-radioactive automatic analysis unit 14 to automatically perform medium-radioactive non-destructive analysis, and after the medium-radioactive automatic analysis is completed or when the medium-radioactive automatic analysis unit 14 cannot perform analysis, the medium-radioactive process samples are transferred to the process sample sending and receiving glove box for manual processing to complete the medium-radioactive automatic analysis or the medium-radioactive automatic analysis unit 14. When the medium-radioactive process samples that cannot be analyzed are moved to the process sample analysis glove box for analysis and then moved back to the process sample sending and receiving glove box, the pneumatic sample delivery system 2 is used to transfer the medium-radioactive process samples that have completed analysis to the isotope analysis unit 17 for isotope analysis; or when the medium-radioactive process samples that have completed medium-radioactive automatic analysis in the process sample sending and receiving glove box or cannot be analyzed by the medium-radioactive automatic analysis unit 14 are manually moved to the process sample pretreatment glove box for pretreatment and then moved back to the process sample sending and receiving glove box, the pneumatic sample delivery system 2 is used to transfer the low-radioactive process samples whose radioactivity has been reduced to a low-radioactive level after pretreatment to the low-radioactive analysis system 6.

[0114] In this embodiment, the intermediate level waste analysis unit 16 includes at least one intermediate level waste glove box analysis line.

[0115] The medium-level three-waste glove box analysis line includes a plurality of three-waste glove boxes connected in sequence, the plurality of three-waste glove boxes include a three-waste sample receiving and sending glove box, a three-waste sample pretreatment glove box and at least one three-waste sample analysis glove box, and the three-waste sample analysis glove box is provided with a three-waste sample analysis instrument.

[0116] The pneumatic sample delivery system 2 is used to transfer the intermediate-level radioactive waste samples in the post-processing process building or the intermediate-level radioactive waste samples formed by pre-processing the high-level radioactive waste samples by the high-level analysis system 3 to the three-waste sample sending and receiving glove box for temporary storage, and is also used to transfer the intermediate-level radioactive waste samples temporarily stored in the three-waste sample sending and receiving glove box to the intermediate-level radioactive automatic analysis unit 14 to automatically perform intermediate-level radioactive non-destructive analysis, and after the intermediate-level radioactive automatic analysis is completed or when the intermediate-level radioactive automatic analysis unit 14 cannot perform analysis, the intermediate-level radioactive waste samples are transferred to the three-waste sample sending and receiving glove box, and the intermediate-level radioactive waste samples in the three-waste sample sending and receiving glove box that have completed the intermediate-level radioactive automatic analysis or cannot be analyzed by the intermediate-level radioactive automatic analysis unit 14 are manually moved to the three-waste sample analysis glove box for analysis,

[0117] When the medium-level radioactive waste samples that have completed the medium-level radioactive automatic analysis in the process sample receiving and sending glove box or cannot be analyzed by the medium-level radioactive automatic analysis unit 14 are manually moved to the three-waste sample pretreatment glove box to complete the pretreatment and then moved back to the three-waste sample receiving and sending glove box, the pneumatic sample delivery system 2 is used to transmit the low-level radioactive waste samples that have completed the pretreatment and whose radioactive activity has been reduced to a low-level level to the low-level analysis system 6.

[0118] In summary, the medium-level radioactive samples are transmitted to the medium-level radioactive automatic analysis unit 14 for automatic analysis through the pneumatic sample delivery system 2. Items that cannot be analyzed in the medium-level radioactive automatic analysis unit 14 are sent to the medium-level radioactive process analysis unit 15, the medium-level radioactive three wastes analysis unit 16 or the isotope analysis unit 17 for analysis according to the source of the samples.

[0119] In this embodiment, the intermediate radioactive samples include intermediate radioactive process samples 39 and intermediate radioactive waste samples 40. The intermediate radioactive process samples 39 are derived from the post-processing main process flow with a radioactivity level greater than or equal to n×10 6 Bq / L(n<10), less than n×10 9 Bq / L (n<10); the medium-level three-waste sample 40 comes from the radioactivity level greater than or equal to n×10 in the post-treatment three-waste process 6 Bq / L(n<10), less than n×10 9 Bq / L (n<10) samples.

[0120] The medium-radiation automatic analysis unit 14 includes an analysis room and medium-radiation automatic analysis instruments arranged in the analysis room, specifically including one or more automatic analyzers such as an automatic L-edge absorption density meter, an automatic energy dispersive X-ray fluorescence analyzer, and an automatic NaIγ spectrometer. The sample is directly sent to the measurement position of the medium-radiation automatic analyzer in the analysis room through the pneumatic sample delivery system 2, and the sample bottle is directly subjected to non-destructive analysis without opening the cover. After the analysis is completed, the sample is returned to the hot chamber through the pneumatic sample delivery system 2.

[0121] The medium-release process analysis unit 15 includes two glove box analysis lines, namely the first medium-release process analysis line 42 and the second medium-release process analysis line 43, which are mainly responsible for the analysis of medium-release samples in the post-processing process that cannot be completed in the medium-release automatic analysis unit 14. The first and second medium-release process analysis lines are arranged in different analysis rooms, and the sample analysis operations are performed in the glove boxes of the first and second medium-release process analysis lines.

[0122] It should be noted that different analytical instruments are installed in each glove box in each glove box analysis line according to the analysis requirements and analysis methods; at the same time, the arrangement order of the glove boxes on the glove box analysis line is set according to the convenience of sample flow and operation.

[0123] In some embodiments, the analysis of samples is mainly carried out in a glove box analysis line, and most of the instruments adopt a modular design, that is, the instrument parts that are in direct contact with the samples are placed inside the glove box, and the instrument control parts and non-contact sample parts are placed outside the glove box, which is convenient for inspection, maintenance and replacement of the instrument and more convenient for personnel operation.

[0124] The medium-level radioactive waste analysis unit 16 includes a glove box analysis line, namely the medium-level radioactive waste analysis line 44, which is mainly responsible for the analysis projects of the post-processed waste samples that cannot be completed in the medium-level radioactive waste automatic analysis unit 14; it also undertakes the analysis tasks of some low-level samples 41, and some medium-level radioactive waste samples can also be analyzed on the medium-level radioactive process analysis line.

[0125] The isotope analysis unit 17 includes a surface thermal ionization mass spectrometer for nuclear material balance analysis and two high-resolution plasma mass spectrometers for criticality safety control analysis.

[0126] like Figure 3 The diagram shows the sample flow of the medium-level analysis system. The medium-level process samples 39 and some low-level samples 41 from the post-processing plant, and some pre-processed high-level process samples 28 are preferentially sent to the sample receiving and sending glove box of the first medium-level process analysis line 42 or the second medium-level process analysis line 43 through the pneumatic sample delivery system 2. The second medium-level process analysis line is mainly used for the analysis of concentrated plutonium samples. The sample bottles are scanned and identified, and the radioactivity or concentration range of the analysis items is determined to determine whether to send them to the medium-level automatic analysis unit 14, or to transfer them to other glove boxes of the first and second medium-level process analysis lines for direct sample analysis or sample pretreatment, or to the low-level analysis system 6 / isotope analysis unit 17.

[0127] The intermediate-level radioactive waste samples 40 and some low-level radioactive waste samples 41 from the waste treatment plant are transported to the sample sending and receiving glove box of the intermediate-level radioactive waste analysis line 45 through the pneumatic sample delivery system 2. After the sample bottles are scanned and identified, they are sent to the intermediate-level radioactive waste automatic analysis unit 14 according to the radioactive activity or concentration range of the analysis items, or transferred to other glove boxes of the waste analysis line for sample pretreatment or direct analysis, or transported to the low-level analysis system 6 / isotope analysis unit 17.

[0128] like Figure 4 As shown in the figure, taking a medium-level radiation process analysis line as an example, the analysis line consists of 5 glove boxes connected in series. The detailed design of the function of each glove box is carried out according to the analysis requirements and methods of the medium-level radiation samples, as well as the convenience of sample flow and operation. With the glove box operating surface as the front, from right to left, there are photometric analysis glove box, acidity analysis glove box, sample sending and receiving glove box, sample pretreatment glove box and gas chromatography glove box.

[0129] The samples are first transferred or temporarily stored in the sending and receiving glove box. Three sets of sending and receiving devices are set in the sending and receiving glove box. The sending and receiving device 1# receives the medium-radioactive samples 39, some pre-treated high-radioactive samples 28, and some low-radioactive samples 41 sent from the post-processing process plant through the pneumatic sample delivery system 2, and scans the sample bottle for identification, and the identification information is uploaded to the laboratory information management system (LIMS). According to the radioactivity or concentration range of the analysis project, it is determined to be sent to the medium-radioactive automatic analysis unit 14 or other analysis room; the sending and receiving device 2# sends the sample to the medium-radioactive automatic analysis position 44 of the medium-radioactive automatic analysis unit 14 for analysis. The medium-radioactive automatic analysis position 44 includes one or more analytical instruments. The automatic analysis instrument is selected according to the specific measurement project. After the analysis is completed, the sample bottle is returned to the sample sending and receiving glove box through the pneumatic sample delivery system 2 for uncapping and sampling analysis; the sending and receiving device 3# mainly performs sample pretreatment (dilution, separation) and then sends it to the isotope analysis unit 17, the low-radioactive analysis system 6 or other medium-radioactive analysis room through the pneumatic sample delivery system 2. After being transferred or temporarily stored at the sending and receiving station, the samples are manually transferred through the channels between the glove boxes to other glove boxes on the analysis line for analysis and measurement.

[0130] It should be noted that, in some embodiments, the sample sending and receiving glove box may include one, two or more sets of sending and receiving devices, not limited to three sets of sending and receiving devices, that is, it is necessary to match the corresponding sending and receiving devices according to the actual process path of the sample.

[0131] With the glove box operation surface as the front, the left and right sides of the sample receiving and sending glove box are the sample pretreatment glove box and the acidity analysis glove box respectively. The gas chromatograph that requires sample pretreatment and sample preparation analysis is concentrated on the left side of the sample pretreatment glove box to avoid detours in sample delivery. The acidity analyzer and photometric analyzer that do not require sample pretreatment analysis are concentrated on the right side of the sample pretreatment glove box. This design allows different analysis items of the same sample to be completed on the same glove box analysis line as much as possible, reducing sample splitting and sample transfer operations within the analysis center, shortening the sample transfer path, and improving sample analysis efficiency.

[0132] In addition, a large number of modular analytical instruments are used in the medium-level radioactive process analysis line, including potentiometric titrators, near-infrared spectrometers, pH meters, sample separation devices, dilution and liquid preparation devices, etc. The parts of the instrument that are in contact with the radioactive liquid, such as the titration table, measurement chamber, ion separation column, etc., are placed in the glove box, and other parts of the instrument, such as detectors, control panels and other electronic parts, are placed outside the glove box. The two parts are connected by cables or reagent tubes, which effectively avoids the influence of the complex environment in the box on the measurement; at the same time, the modular design of the instrument can avoid the formation of solid waste due to radiation damage or radioactive contamination of electronic parts of the instrument, greatly extending the service life of the instrument, simplifying maintenance operations, reducing the amount of solid waste, and improving the safety, convenience and efficiency of analytical laboratory operations.

[0133] In this embodiment, the low-radiation analysis system 6 includes a radioactive source and measurement unit 20, a mass spectrometry unit 21 and other low-radiation analysis units 22.

[0134] The radioactive source and measurement unit 20 is used to determine the radioactivity or nuclide of the low-level sample.

[0135] The mass spectrometry unit 21 is used for the analysis of trace or ultra-trace uranium, neptunium and plutonium and other impurity elements.

[0136] The other low-level analysis units 22 are used for routine analysis of low-level samples.

[0137] Among them, the radioactivity level of low-level sample 41 is less than n×10 6 Bq / L(n<10).

[0138] The radioactive source making and measurement unit 20 includes a variety of instruments for special source making and radioactive activity measurement, such as α spectrometer, low background α, β counter, liquid scintillation spectrometer, NaI γ spectrometer and high purity germanium γ spectrometer.

[0139] The mass spectrometry unit 21 includes three inductively coupled plasma mass spectrometers for analyzing trace or ultra-trace uranium, neptunium and plutonium and other impurity elements.

[0140] The other low-level analysis unit 22 is used for routine analysis of low-level samples and includes two low-level glove box analysis lines.

[0141] In this embodiment, the product analysis system 5 includes a plutonium product analysis unit 18 and a uranium product analysis unit 19.

[0142] The plutonium product analysis unit 18 includes two plutonium product powder glove box analysis lines and one plutonium product coulometric glove box analysis line. The plutonium product powder glove box analysis line is used to perform physical property analysis and non-metallic impurity analysis on plutonium powder, and the plutonium product coulometric analysis line is used to perform dissolution and precise analysis on plutonium powder and filter cake.

[0143] The uranium product analysis unit 19 includes a uranium product powder glove box analysis line and a uranium product potentiometric titration glove box analysis line. The uranium product powder glove box analysis line is used to perform physical property analysis and non-metallic impurity analysis on uranium powder, and the uranium product potentiometric titration glove box analysis line is used to perform dissolution, pretreatment separation and precise uranium content analysis on uranium powder.

[0144] In this embodiment, the laboratory control system 7 includes a standard substance management unit 23, an analytical laboratory information management unit 24, and an analytical reagent and gas cylinder management unit 25.

[0145] The analytical laboratory information management unit 24 is electrically connected to the analytical instruments in the online analytical system 1, the high-radiation analytical system 3, the medium-radiation analytical system 4, the product analytical system 5 and the low-radiation analytical system 6, respectively, and is used to receive the experimental results of the analytical instruments in each analytical system and upload them to the control center.

[0146] The standard material management unit 23 is used to store and manage special standard materials in the nuclear field, including uranium-neptunium-plutonium standard materials, uranium-plutonium isotopes and other special standard materials in the nuclear field, as well as conventional standard materials in analytical chemistry.

[0147] The analytical reagent and gas cylinder management unit 25 is used for storing and managing gas cylinders and analytical reagents of the laboratory platform.

[0148] The analytical laboratory information management unit 24 adopts a laboratory information management system (LIMS), which can receive analysis requirements from the process control position of the control center. After the sample analysis is completed, the analysis results are uploaded to LIMS; LIMS directly collects and obtains the original data of most analytical instruments, realizes the seamless connection between information management and instruments and equipment, and ensures the traceability of the analysis results; and performs quality control and quality management on the circulation of samples within the analytical laboratory and the entire analysis process.

[0149] The analytical reagent and gas cylinder management unit 25 adopts a centralized gas supply system and a centralized reagent storage mode to uniformly manage the laboratory's gas cylinders and analytical reagents.

[0150] In this embodiment, the three waste management system 8 includes a solid waste management unit 26 and a radioactive waste liquid and storage tank exhaust gas treatment unit 27.

[0151] The solid waste management unit 26 is used to uniformly collect and process the solid waste generated by the laboratory platform.

[0152] The radioactive waste liquid and storage tank exhaust gas treatment unit 27 is connected to the online analysis system 1, the high-level analysis system 3, the medium-level analysis system 4, the product analysis system 5 and the low-level analysis system 6 through pipelines, and is used to collect the waste liquids generated by each analysis system into storage tanks according to their types and discharge them uniformly, and at the same time merge the exhaust gases generated by different storage tanks and discharge them uniformly to the exhaust gas main pipe.

[0153] Specifically, the solid waste management unit 26 is mainly responsible for the unified collection and treatment of the intermediate / low-level solid waste generated in the analysis laboratory boxes and rooms.

[0154] The radioactive waste liquid and storage tank exhaust gas treatment unit 27 collects the chamber flushing waste liquid, organic phase analysis waste liquid and aqueous phase analysis waste liquid generated by the analytical laboratory into storage tanks and discharges them uniformly. At the same time, it combines the exhaust gases generated by different storage tanks and discharges them uniformly to the exhaust gas main.

[0155] Compared with the prior art, the technical solution of the present invention has the following beneficial effects:

[0156] The spent fuel reprocessing plant analysis laboratory platform and system design method of the present embodiment adopts a system-analysis line-unit-chamber-analysis instrument design method, and sets eight systems, namely, an online analysis system, a pneumatic sample delivery system, a high-radiation analysis system, a medium-radiation analysis system, a product analysis system, a low-radiation analysis system, a laboratory quality assurance and quality control system, and a three-waste management system. Different functional units are set under the eight systems, analysis lines are set in some functional units, chambers and analysis instruments are set in the analysis lines, and then modular or chamber-integrated design is performed on the analysis chambers and analysis instruments according to different analysis requirements, so that while ensuring sample analysis, supporting conditions such as sample transmission, quality control, and three-waste management are also taken into account.

[0157] Compared with the system design method of the traditional post-processing plant analysis laboratory, the analysis laboratory of this embodiment is generally designed according to high, medium and low radiation laboratories to reduce the radiation hazards of personnel; the online analysis instrument adopts a sleeve design to solve the problem of instrument calibration and maintenance difficulties; different analysis projects of the same sample are completed on the same analysis line, saving sample transportation and delivery manpower; under the premise of meeting the process requirements, non-destructive automatic analysis technology is preferred to improve analysis efficiency; modularization or integrated design of analysis instruments and chambers is carried out to achieve engineering application conditions; at the same time, the laboratory's three wastes treatment and quality control management are taken into account to ensure the normal, stable and safe operation of the post-processing plant analysis laboratory. This system design method can be widely used in radioactive sample analysis environments, especially the analysis of large-scale radioactive samples.

[0158] It is to be understood that the above embodiments are merely exemplary embodiments used to illustrate the principles of the present invention, but the present invention is not limited thereto. For those of ordinary skill in the art, various modifications and improvements can be made without departing from the spirit and essence of the present invention, and these modifications and improvements are also considered to be within the scope of protection of the present invention.

Claims

1. A spent fuel reprocessing plant analysis laboratory system, characterized in that: include: An online analysis system (1), a pneumatic sample delivery system (2) and a laboratory platform, wherein the laboratory platform comprises a high-radiation analysis system (3), a medium-radiation analysis system (4), a product analysis system (5), a low-radiation analysis system (6), a laboratory control system (7) and a three-waste management system (8), The online analysis system (1) comprises an online analysis instrument arranged in each post-processing process plant, which is used to perform online analysis on samples in the corresponding post-processing process plant to complete the online sample analysis task; The pneumatic sample delivery system (2) is connected between each post-processing process building and the laboratory platform, and is used to distribute the samples in the post-processing process building to the corresponding analysis system of the laboratory platform according to the sample analysis task. The high-radiation analysis system (3) is used to receive the high-radiation samples distributed by the pneumatic sample delivery system (2) and analyze the samples to complete the analysis task of the high-radiation samples; The medium-pressure analysis system (4) is used to receive the medium-pressure samples distributed by the pneumatic sample delivery system (2) and analyze the samples to complete the analysis task of the medium-pressure samples; The low-level analysis system (6) is used to receive the low-level samples distributed by the pneumatic sample delivery system (2) and analyze the samples to complete the analysis task of the low-level samples; The product analysis system (5) is used to receive the radioactive element samples distributed by the pneumatic sample delivery system (2) and analyze the samples to complete the analysis task of the radioactive element samples; The laboratory control system (7) is electrically connected to the analytical instruments in the online analysis system (1), the high-radiation analysis system (3), the medium-radiation analysis system (4), the product analysis system (5) and the low-radiation analysis system (6), respectively, and is used to receive the experimental results of the analytical instruments in each analysis system and upload them to the control center, and store and manage the standard substances, gas cylinders and analytical reagents required by the laboratory system; The three waste management system (8) is respectively connected to the high-radiation analysis system (3), the medium-radiation analysis system (4), the low-radiation analysis system (6) and the product analysis system (5), and is used to receive waste generated by analyzing samples of each analysis system and process it; The high-radiation analysis system (3) comprises a high-radiation automatic analysis unit (11) and a high-radiation process analysis unit (12). The high-radiation process analysis unit (12) is used to analyze the high-radiation process samples transmitted by the pneumatic sample delivery system (2). The pneumatic sample delivery system (2) is used to transfer the high-radiation samples in the post-processing process plant to the high-radiation automatic analysis unit (11) for automatic high-radiation non-destructive analysis, and after the high-radiation automatic analysis is completed or when the high-radiation automatic analysis unit (11) is unable to analyze, the high-radiation samples are transferred to the high-radiation process analysis unit (12) according to their source and analysis items. The high-radiation process analysis unit (12) comprises a balance analysis shielding room (30) and a high-radiation process analysis hot room (31), wherein a balance analysis device is arranged in the balance analysis shielding room (30), and the high-radiation process analysis hot room (31) is divided into a first automatic transfer area (34) and a first manual analysis area (35) by a partition. The pneumatic sample delivery system (2) is used to transfer the high-radiation process samples in the post-processing process building to the first automatic transfer area (34) for temporary storage, and is also used to transfer the high-radiation process samples temporarily stored in the first automatic transfer area (34) to the high-radiation automatic analysis position (38), and is also used to transfer the high-radiation process samples to the first automatic transfer area (34) for temporary storage after the high-radiation automatic analysis is completed or when the high-radiation automatic analysis unit (11) is unable to analyze, and is also used to manually move the high-radiation process samples temporarily stored in the first automatic transfer area (34) to the first manual analysis area (35) for acid analysis or pretreatment, and then transfer the high-radiation process samples after acid analysis to the balance analysis shielding room (30), and transfer the high-radiation process samples after pretreatment to the medium-radiation analysis system (4) or the low-radiation analysis system (6); the balance analysis equipment is used to perform balance analysis on the high-radiation process samples in the balance analysis shielding room (30).

2. The spent fuel reprocessing plant analysis laboratory system according to claim 1, characterized in that: The high-level radioactive analysis system (3) further comprises a high-level radioactive waste liquid analysis unit (13), The high-level waste liquid analysis unit (13) is used to analyze the high-level waste samples transmitted by the pneumatic sample delivery system (2). The pneumatic sample delivery system (2) is used to transfer the high-radiation samples in the post-processing process building to the high-radiation automatic analysis unit (11) for automatic high-radiation non-destructive analysis, and after the high-radiation automatic analysis is completed or when the high-radiation automatic analysis unit (11) is unable to analyze, the high-radiation samples are transferred to the high-radiation waste liquid analysis unit (13) according to their source and analysis items.

3. The spent fuel reprocessing plant analysis laboratory system according to claim 2, characterized in that: The high-radiation automatic analysis unit (11) comprises an analysis room and a plurality of automatic analyzers arranged in the analysis room. A high-radiation automatic analysis post (38) is arranged in the analysis room. The pneumatic sample delivery system (2) is used to transmit the high-radiation samples in the post-processing process workshop to the high-radiation automatic analysis post (38). The automatic analyzers are used to automatically perform corresponding non-destructive analysis on the high-radiation samples on the high-radiation automatic analysis post (38).

4. The spent fuel reprocessing plant analysis laboratory system according to claim 2, characterized in that: The high-level radioactive waste liquid analysis unit (13) comprises a multi-element analysis shielded room (33) and a high-level radioactive waste liquid analysis hot room (32), wherein an anion and cation analysis device is arranged in the multi-element analysis shielded room (33), and the high-level radioactive waste liquid analysis hot room (32) is divided into a second automatic transfer area (37) and a second manual analysis area (36) by a partition. The pneumatic sample delivery system (2) is used to transfer high-level radioactive waste samples in the post-processing process building to the second automatic transfer area (37) for temporary storage, and is also used to transfer the high-level radioactive waste samples temporarily stored in the second automatic transfer area (37) to the high-level radioactive automatic analysis position (38), and is also used to transfer the high-level radioactive waste samples to the second automatic transfer area (37) for temporary storage after the high-level radioactive automatic analysis is completed or when the high-level radioactive automatic analysis unit (11) cannot perform analysis, and is also used to manually move the high-level radioactive waste samples temporarily stored in the second automatic transfer area (37) to the second manual analysis area (36) for acid analysis, salt content analysis or pretreatment, and then transfer the high-level radioactive waste samples after acid analysis or salt content analysis to the multi-element analysis shielding room (33), and transfer the pretreated high-level radioactive waste samples to the medium-level analysis system (4) or the low-level analysis system (6); the anion and cation analysis equipment is used to perform anion and cation analysis on the high-level radioactive waste samples in the multi-element analysis shielding room (33).

5. The spent fuel reprocessing plant analysis laboratory system according to claim 4, characterized in that: The medium-level radioactive analysis system (4) comprises a medium-level radioactive automatic analysis unit (14), a medium-level radioactive process analysis unit (15), a medium-level radioactive three wastes analysis unit (16) and an isotope analysis unit (17). The pneumatic sample delivery system (2) is used to transfer the intermediate-level radioactive samples in the post-processing process building or the intermediate-level radioactive samples whose radioactivity is reduced to the intermediate-level radioactive level by pre-processing the high-level radioactive samples by the high-level radioactive analysis system (3) to the intermediate-level radioactive automatic analysis unit (14) to automatically perform intermediate-level radioactive non-destructive analysis, and after the intermediate-level radioactive automatic analysis is completed or when the intermediate-level radioactive automatic analysis unit (14) is unable to perform analysis, the intermediate-level radioactive samples are transferred to the intermediate-level radioactive process analysis unit (15) or the intermediate-level radioactive three-waste analysis unit (16) according to their sources and analysis items. The intermediate-level radioactive process analysis unit (15) is used to analyze the intermediate-level radioactive process samples transmitted by the pneumatic sample delivery system (2), and the intermediate-level radioactive three wastes analysis unit (16) is used to analyze the intermediate-level radioactive three wastes samples transmitted by the pneumatic sample delivery system (2). The pneumatic sample delivery system (2) is also used to transmit the intermediate-level radioactive process sample to the isotope analysis unit (17) for isotope analysis after the intermediate-level radioactive process sample is analyzed by the intermediate-level radioactive process analysis unit (15).

6. The spent fuel reprocessing plant analysis laboratory system according to claim 5, characterized in that: The medium-level process analysis unit (15) comprises at least one medium-level process glove box analysis line, The medium-release process glove box analysis line includes a plurality of process glove boxes connected in sequence, the plurality of process glove boxes including a process sample receiving and sending glove box, a process sample pretreatment glove box and at least one process sample analysis glove box, wherein the process sample analysis glove box is provided with a process sample analysis instrument. The pneumatic sample delivery system (2) is used to transfer the medium-radioactive process samples in the post-processing process building or the medium-radioactive process samples formed by pre-processing the high-radioactive process samples by the high-radioactive analysis system (3) to a process sample sending and receiving glove box for temporary storage, and is also used to transfer the medium-radioactive process samples temporarily stored in the process sample sending and receiving glove box to the medium-radioactive automatic analysis unit (14) to automatically perform medium-radioactive non-destructive analysis, and after the medium-radioactive automatic analysis is completed or when the medium-radioactive automatic analysis unit (14) cannot perform analysis, transfer the medium-radioactive process samples to the process sample sending and receiving glove box for manual processing to complete the medium-radioactive automatic analysis or the medium-radioactive automatic analysis unit (14). When the medium-radioactive process sample that cannot be analyzed is moved to the process sample analysis glove box for analysis and then moved back to the process sample sending and receiving glove box, the pneumatic sample delivery system (2) is used to transfer the medium-radioactive process sample that has completed analysis to the isotope analysis unit (17) for isotope analysis; or when the medium-radioactive process sample that has completed medium-radioactive automatic analysis in the process sample sending and receiving glove box or cannot be analyzed by the medium-radioactive automatic analysis unit (14) is manually moved to the process sample pretreatment glove box for pretreatment and then moved back to the process sample sending and receiving glove box, the pneumatic sample delivery system (2) is used to transfer the low-radioactive process sample that has completed pretreatment and whose radioactivity has been reduced to a low-radioactive level to the low-radioactive analysis system (6).

7. The spent fuel reprocessing plant analysis laboratory system according to claim 6, characterized in that: The intermediate-level three-waste analysis unit (16) comprises at least one intermediate-level three-waste glove box analysis line, The medium-level three-waste glove box analysis line includes a plurality of three-waste glove boxes connected in sequence, the plurality of three-waste glove boxes include a three-waste sample receiving and sending glove box, a three-waste sample pretreatment glove box and at least one three-waste sample analysis glove box, and the three-waste sample analysis glove box is provided with a three-waste sample analysis instrument. The pneumatic sample delivery system (2) is used to transfer the intermediate-level radioactive waste samples in the post-processing process building or the intermediate-level radioactive waste samples formed by pre-treating the high-level radioactive waste samples by the high-level analysis system (3) to the intermediate-level radioactive waste sample sending and receiving glove box for temporary storage, and is also used to transfer the intermediate-level radioactive waste samples temporarily stored in the intermediate-level radioactive waste sample sending and receiving glove box to the intermediate-level radioactive waste automatic analysis unit (14) to automatically perform intermediate-level radioactive non-destructive analysis, and after the intermediate-level radioactive waste automatic analysis is completed or when the intermediate-level radioactive waste automatic analysis unit (14) cannot perform analysis, the intermediate-level radioactive waste samples are transferred to the intermediate-level radioactive waste sample sending and receiving glove box, and the intermediate-level radioactive waste samples in the intermediate-level radioactive waste sample sending and receiving glove box that have completed the intermediate-level radioactive waste automatic analysis or cannot be analyzed by the intermediate-level radioactive waste automatic analysis unit (14) are manually moved to the intermediate-level waste sample analysis glove box for analysis, When the medium-level radioactive waste samples that have completed the medium-level radioactive automatic analysis in the process sample receiving and sending glove box or cannot be analyzed by the medium-level radioactive automatic analysis unit (14) are manually moved to the three-waste sample pretreatment glove box to complete the pretreatment and then moved back to the three-waste sample receiving and sending glove box, the pneumatic sample delivery system (2) is used to transfer the low-level radioactive waste samples that have completed the pretreatment and whose radioactive activity has been reduced to a low-level level to the low-level analysis system (6).

8. The spent fuel reprocessing plant analysis laboratory system according to claim 7, characterized in that: The low-radiation analysis system (6) comprises a radioactive source and measurement unit (20), a mass spectrometry unit (21) and other low-radiation analysis units (22). The radioactive source and measurement unit (20) is used to measure the radioactivity or nuclide of the low-radiation sample. The mass spectrometry unit (21) is used for analyzing trace or ultra-trace uranium, neptunium and plutonium and other impurity elements. The other low-radiation analysis unit (22) is used for routine analysis of low-radiation samples.

9. The spent fuel reprocessing plant analysis laboratory system according to any one of claims 1 to 8, characterized in that: The product analysis system (5) comprises a plutonium product analysis unit (18) and a uranium product analysis unit (19), The plutonium product analysis unit (18) comprises a plutonium product powder glove box analysis line and a plutonium product coulometric glove box analysis line, wherein the plutonium product powder glove box analysis line is used for performing physical property analysis and non-metallic impurity analysis on plutonium powder, and the plutonium product coulometric analysis line is used for dissolving and precisely analyzing plutonium powder and filter cake; The uranium product analysis unit (19) comprises a uranium product powder glove box analysis line and a uranium product potentiometric titration glove box analysis line. The uranium product powder glove box analysis line is used to perform physical property analysis and non-metallic impurity analysis on uranium powder, and the uranium product potentiometric titration glove box analysis line is used to perform dissolution, pretreatment separation and precise uranium content analysis on uranium powder.

10. The spent fuel reprocessing plant analysis laboratory system according to any one of claims 1 to 8, characterized in that: The laboratory control system (7) comprises a standard material management unit (23), an analytical laboratory information management unit (24) and an analytical reagent and gas cylinder management unit (25). The analytical laboratory information management unit (24) is electrically connected to the analytical instruments in the online analytical system (1), the high-radiation analytical system (3), the medium-radiation analytical system (4), the product analytical system (5) and the low-radiation analytical system (6), respectively, and is used to receive the experimental results of the analytical instruments in each analytical system and upload them to the control center. The standard substance management unit (23) is used to store and manage special standard substances in the nuclear field and conventional standard substances in analytical chemistry. The analytical reagent and gas cylinder management unit (25) is used to store and manage gas cylinders and analytical reagents on the laboratory platform.

11. The spent fuel reprocessing plant analysis laboratory system according to any one of claims 1 to 8, characterized in that: The three waste management system (8) comprises a solid waste management unit (26) and a radioactive waste liquid and storage tank exhaust gas treatment unit (27). The solid waste management unit (26) is used to uniformly collect and process the solid waste generated by the laboratory platform. The radioactive waste liquid and storage tank exhaust gas treatment unit (27) is connected to the online analysis system (1), the high-radiation analysis system (3), the medium-radiation analysis system (4), the product analysis system (5) and the low-radiation analysis system (6) through pipelines, and is used to collect the waste liquid generated by each analysis system into storage tanks according to their types and discharge them uniformly, and at the same time, merge the exhaust gases generated by different storage tanks and discharge them uniformly to the exhaust gas main pipe.

Images