CN110853779A - Nuclear fuel irradiation test method - Google Patents
Nuclear fuel irradiation test method Download PDFInfo
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- CN110853779A CN110853779A CN201911141674.2A CN201911141674A CN110853779A CN 110853779 A CN110853779 A CN 110853779A CN 201911141674 A CN201911141674 A CN 201911141674A CN 110853779 A CN110853779 A CN 110853779A
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- irradiation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a nuclear fuel irradiation test method, which belongs to the technical field of research on reactor fuel irradiation and comprises the following steps: fuel encapsulation, namely filling fuel into a fuel assembly with a pre-processed and welded unidirectional opening, arranging the assemblies, and arranging the two assemblies into a group which are arranged in the clamping block assembly side by side; the test section is placed into the reactor and is hung from the reactor top, the irradiation test section is positioned in the active section of the reactor core, and the irradiation device section is hermetically connected with the reactor top through a flange; checking in the pile, checking and monitoring relevant parameters after the fuel is placed in the pile along with the irradiation device; and (4) discharging the fuel at the test section, wherein the fuel after irradiation reaches the irradiation neutron fluence specified in the test and then is discharged. Aiming at the irradiation requirement of the novel nuclear fuel in the reactor, the invention develops a method which is more economic and reliable, can reflect the irradiation condition of the nuclear fuel in the reactor in real time and accurately obtains the relevant irradiation parameters.
Description
Technical Field
The invention relates to the technical field of research on reactor fuel irradiation, in particular to a nuclear fuel irradiation test method.
Background
With the brand-new development period of the nuclear power industry, nuclear power projects which are operated in China, under construction and planned to start work are increased year by year, the proportion of nuclear energy in energy consumption is continuously increased, and the updating and updating of the nuclear power are accelerated. Meanwhile, the development and research of the new generation nuclear power station has larger demand and higher requirement on novel nuclear materials and nuclear fuels, and particularly has more urgent demand on more economical, safer and high-fuel-consumption nuclear fuels. In the research and development process of new nuclear fuel, in-pile irradiation is carried out, after the in-pile irradiation reaches the target fluence, the comprehensive performance of the fuel is evaluated by adopting a post-irradiation inspection means.
At present, the structural forms of nuclear fuels are more, and the specific irradiation method is different from the fuel structure according to the experimental purpose. However, the method is mainly used for placing new fuel in an irradiation device for irradiation, taking post-irradiation inspection as a main performance evaluation means, carrying out low-concentration nuclear fuel on an advanced test reactor of the national laboratory of Edwardsiella in the United states, placing the low-concentration nuclear fuel in the irradiation device for irradiation in the reactor, and determining parameters such as burnup, temperature, fission rate and the like by means of a computer and real-time monitoring of primary loop water so as to evaluate the performance of the fuel. However, in the above manner, the former cannot reflect the irradiation condition of the fuel in the stack in real time, and the latter relies too much on computer software, so that the calculated value cannot be effectively compared with the test value. Therefore, there is a need to develop a more efficient, reliable, and real-time irradiation of nuclear fuel in a reactor.
Disclosure of Invention
The invention discloses a nuclear fuel irradiation testing method, which is a method for developing a method which is more economical and reliable, can reflect the irradiation condition of nuclear fuel in a reactor in real time, ensures the safety in the reactor and accurately acquires relevant irradiation parameters aiming at the irradiation requirement of novel nuclear fuel in the reactor.
In order to achieve the above object, the present application provides a nuclear fuel irradiation testing method, comprising the steps of:
1) fuel encapsulation, namely filling fuel into a fuel assembly with a pre-processed and assembled and welded unidirectional opening, carrying out flaw detection monitoring on a welding line of the fuel assembly before filling the fuel, and carrying out laser character numbering; flaw detection monitoring is carried out on the welding seam again after packaging, leakage of fuel assemblies is avoided when fuel is irradiated in a stack, the fuel is directly contacted with water in the same loop, and the packaged fuel is collectively called as an assembly;
2) the assembly is arranged, two assemblies are in a group and are arranged in the clamping block assembly side by side, the height of the clamping block assembly is greater than the length of the assembly, the assembly is in clearance fit with the groove of the clamping block assembly, the assembly is ensured to be smoothly separated from the clamping block assembly after irradiation is finished, but the assembly is ensured not to deviate or misplace in the assembly process, cooling water channels are reserved on two sides of the assembly, and the installation position of the assembly is recorded; stacking the clamp block components provided with the assemblies inside an outer cylinder of an irradiation test section in sequence, wherein 20 assemblies after arrangement are equally divided into two groups, and each group is stacked axially in parallel;
3) putting the test section into a reactor, coaxially assembling an irradiation test section provided with a clamping block assembly and an irradiation device section, sleeving the tail end of the irradiation device section on the outer side of an upper connector at the top of the irradiation test section, in clearance fit with the upper connector, axially fixing the irradiation device section and the irradiation test section by using a steel wire rope, then installing temperature detection points and assembling sampling pipes at an inlet and an outlet of the test section, finally, hanging the test section from the reactor top, wherein the irradiation test section is positioned at an active section of a reactor core, and the irradiation device section is hermetically connected with the reactor top through a flange;
4) in-reactor examination, after the fuel is placed into the reactor along with the irradiation device, the fuel is positioned in an active section area of the reactor core, and when the fuel is irradiated in the reactor, the flow of the primary loop water entering the irradiation device is regulated, the heat exchange quantity of the primary loop water and the fuel is controlled, and the assembly is ensured to be positioned in a low-temperature water environment; in addition, the temperature of the inlet and the outlet of the flow assembly in the irradiation test section is monitored in real time, loop water samples in the inlet and the outlet are collected, the water quality is analyzed, and the actual parameters in the reactor are fed back in time, so that the protection purpose is achieved;
5) and (3) discharging the reactor at the test section, stopping the reactor after the fuel reaches the irradiation neutron fluence specified in the test after the irradiation of the 12-15 furnace section, and hoisting the reactor after the reactor core cooling period.
After the assembly is arranged in the clamping block assembly, the end part of the clamping block assembly is 0.5 mm-1 mm higher than the assembly;
the tail end of the irradiation device section is sleeved outside the upper joint of the irradiation test section, and the contact length of the tail end of the irradiation device section and the outer side of the upper joint is 20-52 mm.
The length of the fuel section in the irradiation test section is not more than 1000 mm.
The temperature of the surface of the assembly is controlled to be 100-150 ℃.
One or more technical solutions provided by the present application have at least the following technical effects or advantages:
the invention responds to the research and development requirements of novel nuclear fuel at present, and provides a method capable of reflecting the irradiation condition of the nuclear fuel in a reactor in real time and accurately acquiring related irradiation parameters aiming at the irradiation environment of HFETR.
In the actual use process, the invention has the following beneficial effects:
1) the invention directly adopts the primary loop water to immerse the assembly for cooling, takes away the surface heat of the assembly, and ensures the safety in the reactor while reaching the temperature required by the test;
2) thermocouples are arranged at an inlet and an outlet of an irradiation test section, and the temperature of a primary loop water passing through an assembly is monitored in real time; meanwhile, the temperature monitoring can provide a basis for fuel consumption calculation and reflect the safety in the reactor in real time;
3) according to the invention, the sampling pipes are arranged at the inlet and the outlet of the irradiation test section, so that the water quality change of the assembly flowing through the irradiation test section can be monitored in real time, and test comparison input is provided for monitoring after irradiation; meanwhile, whether the assembly is damaged or not is monitored constantly, and safety in the reactor is guaranteed;
4) the invention adopts the irradiation form of the sun and the shade, so that the fuel irradiation is more uniform, and the performance analysis after the fuel irradiation is facilitated.
5) The invention can realize irradiation of various assemblies at one time, shorten the axial direction of a test, mutually refer the various assemblies, and obtain more comprehensive test data, and is more economic and reliable compared with the prior art.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiments of the invention and together with the description serve to explain the principles of the invention;
FIG. 1 is a schematic flow diagram of a nuclear fuel irradiation test method of the present application;
fig. 2 is a schematic structural view of a clamp block assembly in the present application.
Detailed Description
In order that the above objects, features and advantages of the present invention can be more clearly understood, a more particular description of the invention will be rendered by reference to the appended drawings. It should be noted that the embodiments and features of the embodiments of the present application may be combined with each other without conflicting with each other.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention, however, the present invention may be practiced in other ways than those specifically described and thus the scope of the present invention is not limited by the specific embodiments disclosed below.
Referring to fig. 1, an embodiment of the present invention provides a nuclear fuel irradiation testing method, including the following steps:
1) fuel encapsulation, namely filling fuel into a fuel assembly with a pre-processed and assembled and welded unidirectional opening (the unidirectional opening is designed to reduce the welding frequency after fuel encapsulation), carrying out flaw detection monitoring on a welding line of the fuel assembly before filling the fuel, and exciting a word number; flaw detection monitoring is carried out on the welding seam again after packaging, leakage of fuel assemblies is avoided when fuel is irradiated in a stack, the fuel is directly contacted with water in the same loop, and the packaged fuel is collectively called as an assembly;
2) the assembly is arranged, two assemblies are a group, and are arranged in the clamping block assembly side by side, (the purpose of the design is that the space in the duct is limited, the space in the duct is favorably and fully utilized by arranging the assemblies side by side, and the cooling water is ensured to fully flow through the assemblies), the height of the clamping block assembly is more than the length of the assemblies, the assemblies and the grooves of the clamping block assembly are in clearance fit, the assemblies and the clamping block assembly are ensured to be smoothly separated after the irradiation is finished, but the positions of the assemblies are ensured not to be deviated or misplaced in the assembling process, cooling water channels are reserved on two sides of the assemblies, and the installation; stacking the clamp block components provided with the assemblies inside an outer cylinder of an irradiation test section in sequence, wherein 20 assemblies after arrangement are equally divided into two groups, and each group is stacked axially in parallel; (the design is divided into two groups of side by side, can make full use of the pore space, axially stack, reserve the channel for cooling water flow and other measurement and control devices)
3) Putting the test section into a reactor, coaxially assembling an irradiation test section provided with a clamping block assembly and an irradiation device section, sleeving the tail end of the irradiation device section on the outer side of an upper connector at the top of the irradiation test section, in clearance fit with the upper connector, axially fixing the irradiation device section and the irradiation test section by using a steel wire rope, then installing temperature detection points and assembling sampling pipes at an inlet and an outlet of the test section, finally, hanging the test section from the reactor top, wherein the irradiation test section is positioned at an active section of a reactor core, and the irradiation device section is hermetically connected with the reactor top through a flange;
4) in-reactor examination, after the fuel is placed into the reactor along with the irradiation device, the fuel is positioned in an active section area of the reactor core, and when the fuel is irradiated in the reactor, the flow of the primary loop water entering the irradiation device is regulated, the heat exchange quantity of the primary loop water and the fuel is controlled, and the assembly is ensured to be positioned in a low-temperature water environment; in addition, the temperature of the inlet and the outlet of the flow assembly in the irradiation test section is monitored in real time, loop water samples in the inlet and the outlet are collected, the water quality is analyzed, and the actual parameters in the reactor are fed back in time, so that the protection purpose is achieved;
5) and (3) discharging the reactor at the test section, stopping the reactor after the fuel reaches the irradiation neutron fluence specified in the test after the irradiation of the 12-15 furnace section, and hoisting the reactor after the reactor core cooling period.
After the assembly is arranged in the clamping block assembly, the end part of the clamping block assembly is 0.5 mm-1 mm higher than the assembly; the purpose of the design is that a plurality of clamp block assemblies are axially stacked, the end parts of the clamp block assemblies are 0.5-1 mm higher than the assembly parts, on one hand, rigid contact between the assembly parts is avoided, the assembly parts are prevented from being damaged by extrusion, the end parts of the assembly parts are also in contact with cooling water, on the other hand, the clamp block assemblies are tightly attached to each other, and the total height of the clamp block assemblies is not more than an active area.
The tail end of the irradiation device section is sleeved outside the upper joint of the irradiation test section, and the contact length of the tail end of the irradiation device section and the outer side of the upper joint is 20-52 mm.
The length of the fuel section in the irradiation test section is not more than 1000 mm.
The temperature of the surface of the assembly is controlled to be 100-150 ℃.
Referring to fig. 2, the clamping block assembly of the present invention includes: 1-upper fixed blocks A, 2-upper fixed blocks B, 3-lower fixed blocks A, 4-lower fixed blocks B, wherein the upper fixed blocks and the lower fixed blocks are of semi-cylindrical structures, semicircular bosses are arranged at the bottom ends of the upper fixed blocks A and the upper fixed blocks B, and semicircular grooves are machined at the upper ends of the lower fixed blocks A and the lower fixed blocks B. The upper fixing block A and the upper fixing block B are spliced into a cylinder, and the lower fixing block A and the lower fixing block B are spliced into a cylinder. During assembly, the bosses of the upper fixing block A and the upper fixing block B are clamped in the grooves of the lower fixing block A and the lower fixing block B to form a clamping block assembly. Through designing mosaic structure, reduced the processing degree of difficulty to the straightness accuracy of fixed block top side groove and round hole has been guaranteed, in addition, such design not only can fix the sub-assembly, simultaneously, can guarantee that the sub-assembly has the cooling water to flow through all around.
While preferred embodiments of the present invention have been described, additional variations and modifications in those embodiments may occur to those skilled in the art once they learn of the basic inventive concepts. Therefore, it is intended that the appended claims be interpreted as including preferred embodiments and all such alterations and modifications as fall within the scope of the invention.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (10)
1. A nuclear fuel irradiation test method, comprising:
step 1: encapsulating fuel in fuel assemblies to form assemblies, obtaining a plurality of assemblies;
step 2: mounting the assembly 2 in a clamping block assembly to obtain a plurality of clamping block assemblies provided with the assembly, and sequentially stacking the clamping block assemblies provided with the assembly in the outer barrel of the irradiation test section;
and step 3: coaxially assembling an irradiation test section provided with a clamping block assembly and an irradiation device section, sleeving the tail end of the irradiation device section on the outer side of an upper connector at the top of the irradiation test section, axially fixing the irradiation device section and the irradiation test section, hanging the irradiation test section and the irradiation device from a reactor top, placing the irradiation test section in an active section of a reactor core, and hermetically connecting the irradiation device section with the reactor top through a flange;
and 4, step 4: the irradiation in the reactor simultaneously adjusts the water flow of a primary circuit entering the irradiation device, and controls the heat exchange quantity of the primary circuit water and the fuel, so that the assembly is in a low-temperature water environment.
2. The nuclear fuel irradiation test method according to claim 1, wherein the step 1 specifically includes:
filling fuel into a fuel assembly with a pre-processed and assembled and welded unidirectional opening, carrying out flaw detection monitoring on a welding line of the fuel assembly before filling the fuel, and carrying out laser character numbering; and (4) carrying out flaw detection monitoring on the welding seam again after packaging, wherein the packaged fuel is collectively called as an assembly.
3. The nuclear fuel irradiation test method of claim 1, wherein the height of the clamp block assembly is greater than 2 combined lengths of the assembly and the assembly is in clearance fit with the groove of the clamp block assembly.
4. The method for testing irradiation of nuclear fuel according to claim 1, wherein cooling water passages are left on both sides of the assembly.
5. The method for the irradiation test of nuclear fuel as claimed in claim 1, wherein the completed assembly arranged inside the outer cylinder of the irradiation test section in step 2 is divided into two groups, and each group is stacked in parallel axially.
6. The method for the irradiation test of the nuclear fuel according to claim 1, wherein before the irradiation test section and the irradiation device are hung on the top of the reactor in the step 3, the method further comprises the steps of installing temperature detection points and assembling sampling tubes at the inlet and the outlet of the irradiation test section.
7. The nuclear fuel irradiation test method according to claim 1, wherein the step 4 further includes: and monitoring the temperature of the inlet and the outlet of the flow-through assembly in the irradiation test section in real time, collecting loop water samples at the inlet and the outlet of the irradiation test section, analyzing the water quality, and feeding back actual parameters in the reactor in time.
8. The nuclear fuel irradiation test method according to claim 1, wherein after the assembly is installed in the block assembly, the end of the block assembly is 0.5mm to 1mm higher than the assembly; the tail end of the irradiation device section is sleeved outside the upper joint of the irradiation test section, and the contact length of the tail end of the irradiation device section and the outer side of the upper joint is 20-52 mm.
9. The nuclear fuel irradiation test method according to claim 1, wherein the fuel section length in the irradiation test section is not more than 1000 mm.
10. The method for the irradiation test of nuclear fuel according to claim 1, wherein the temperature of the surface of the assembly is controlled to be 100 to 150 ℃.
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| CN201911141674.2A CN110853779A (en) | 2019-11-20 | 2019-11-20 | Nuclear fuel irradiation test method |
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Cited By (6)
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| CN111398010A (en) * | 2020-03-16 | 2020-07-10 | 中广核研究院有限公司 | Irradiation device for studying chemical diffusion between materials |
| CN113418462A (en) * | 2021-06-23 | 2021-09-21 | 中国核动力研究设计院 | Measuring device and testing device for researching deformation of in-pile material |
| CN113470862A (en) * | 2021-07-23 | 2021-10-01 | 中国核动力研究设计院 | Irradiation device based on component mesopores |
| CN115171929A (en) * | 2021-04-01 | 2022-10-11 | 中核核电运行管理有限公司 | Method for processing small gap between water supply branch pipe and fuel channel of heavy water reactor set |
| CN115762833A (en) * | 2022-11-17 | 2023-03-07 | 中国核动力研究设计院 | Lifting type irradiation device suitable for research reactor and irradiation temperature control method |
| CN115985546A (en) * | 2022-11-07 | 2023-04-18 | 中国核动力研究设计院 | Half-and-half type partitioned temperature control irradiation device |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111398010A (en) * | 2020-03-16 | 2020-07-10 | 中广核研究院有限公司 | Irradiation device for studying chemical diffusion between materials |
| CN115171929A (en) * | 2021-04-01 | 2022-10-11 | 中核核电运行管理有限公司 | Method for processing small gap between water supply branch pipe and fuel channel of heavy water reactor set |
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| CN113470862B (en) * | 2021-07-23 | 2023-11-17 | 中国核动力研究设计院 | Irradiation device based on component mesopores |
| CN115985546A (en) * | 2022-11-07 | 2023-04-18 | 中国核动力研究设计院 | Half-and-half type partitioned temperature control irradiation device |
| CN115985546B (en) * | 2022-11-07 | 2024-03-19 | 中国核动力研究设计院 | Half-and-half type partition temperature control irradiation device |
| CN115762833A (en) * | 2022-11-17 | 2023-03-07 | 中国核动力研究设计院 | Lifting type irradiation device suitable for research reactor and irradiation temperature control method |
| CN115762833B (en) * | 2022-11-17 | 2024-01-30 | 中国核动力研究设计院 | Lifting type irradiation device suitable for research pile and irradiation temperature control method |
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Application publication date: 20200228 |