CN111627581B - Method and device for measuring fast reactor power distribution - Google Patents
Method and device for measuring fast reactor power distribution Download PDFInfo
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- CN111627581B CN111627581B CN202010520473.XA CN202010520473A CN111627581B CN 111627581 B CN111627581 B CN 111627581B CN 202010520473 A CN202010520473 A CN 202010520473A CN 111627581 B CN111627581 B CN 111627581B
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- 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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Abstract
The invention discloses a method for measuring fast reactor power distribution, which comprises the following steps: arranging a collimation hole on the side wall of a transfer chamber of the fast reactor, wherein the collimation hole penetrates through the side wall of the transfer chamber; a gamma ray detection device is arranged outside the side wall of the transfer chamber and is used for detecting gamma rays from the collimation hole; operating a fuel assembly of a fast reactor for a certain time; stopping the fast reactor; transporting the fuel assembly to a transfer mechanism location within the transfer chamber aligned with the alignment aperture; measuring parameters of gamma rays from the fuel assembly by using a gamma ray detection device; and calculating the power distribution of the fast reactor according to the measured parameters of the gamma rays. The method is simple and easy to implement, and does not need to design and manufacture special irradiation experiment components and related equipment, so that the cost is lower, the operation is simple and convenient, no additional radioactive waste is generated, and the safety is improved. A related apparatus for performing the above method is also disclosed.
Description
Technical Field
The present invention relates to the field of nuclear reactors, and more particularly to a method for measuring and calculating the power distribution of a reactor and the related apparatus for implementing the method.
Background
With the development of economy in China, the demand on power supply is greater and greater, and non-fossil energy gradually replaces the role of fossil energy by virtue of the advantages of cleanness and reproducibility. Nuclear power is becoming a new favorite of the energy community by virtue of its advantages in terms of resources, environment and economy. With the development of nuclear energy, the nuclear safety problem is paid more and more attention by people, and the requirements on effective control and safety control of a nuclear power station are higher and higher.
The reactor core power distribution is a key parameter related to the safe operation of the reactor, and the reactor core power distribution needs to be measured before the full-power operation of a general nuclear power plant. Pressurized water reactor nuclear power plants typically employ either a mobile miniature fission ionization chamber or a stationary white powered detector to perform power distribution measurements, which typically require dedicated ports in the reactor core and the installation of specialized instrumentation. The power distribution in the circumferential direction and the axial direction inside the core of the reactor is measured by the self-powered probe, and the measurement information of the power distribution is used for determining whether the reactor operates in the limit range of the nuclear power distribution so as to ensure the operation safety of the nuclear reactor.
However, in a fast reactor nuclear power plant, a dedicated probe hole cannot be provided in the core, and the core is in a high temperature environment, so that a general core power distribution measurement method adopted by a pressurized water reactor power plant cannot be adopted. The fast reactor core usually adopts a detection sheet activation method to measure the power distribution of the fast reactor core, but the method has the disadvantages of complicated process, long time consumption, higher irradiation dosage born by experimenters, need to customize various special tools and generate a large amount of radioactive wastes. For example, the main process links of measuring power distribution by the detection sheet activation method include selection and preparation of detection sheets, packaging of an irradiation device, stacking of experimental components and replacement of in-stack components, low-power irradiation, disassembly of the irradiation device after irradiation, activity measurement of a large number of detection sheets, and the like. In addition, the detection patch activation method requires the design and manufacture of a dedicated irradiation experiment assembly, making such a measurement method costly.
Therefore, it is desirable to provide a method for measuring the power distribution of the fast reactor core, which is simple in operation, safe and reliable, and has reduced cost.
Disclosure of Invention
In order to solve at least one of the above technical problems, embodiments of the present invention provide a method for measuring a fast reactor power distribution, which directly measures an activity distribution of a specific fission product of a fuel assembly after low power irradiation by using a gamma ray detector, obtains a fission reactivity distribution of a core after performing correlation correction, and obtains a fast reactor power distribution by performing normalization processing on the fission reactivity distribution of the core after correction, so as to replace a conventional method for measuring a fast reactor power distribution by using a probe activation method.
The invention provides a method for measuring fast reactor power distribution, which comprises the following steps:
arranging an alignment hole on the side wall of a transfer chamber of the fast reactor, wherein the alignment hole penetrates through the side wall of the transfer chamber;
arranging a gamma ray detection device outside the side wall of the transfer chamber, wherein the gamma ray detection device is used for detecting gamma rays from the collimation hole;
operating a fuel assembly of the fast reactor for a certain time;
stopping the fast reactor;
transporting the fuel assembly to a transfer mechanism location within the transfer chamber aligned with the alignment aperture;
measuring parameters of gamma rays from the fuel assembly by using the gamma ray detection device; and
and calculating the power distribution of the fast reactor according to the measured parameters of the gamma rays.
According to a preferred embodiment of the method for measuring the fast reactor power distribution, a filtering component capable of filtering low-level gamma rays is arranged at the position, close to the gamma ray detection device, of the collimation hole.
In another preferred embodiment of the method for measuring a fast reactor power distribution according to the invention, the filter member comprises a sheet filter made of stainless steel or lead.
According to a further preferred embodiment of the method for measuring the power distribution of a fast reactor according to the present invention, the step of operating the fuel assemblies of said fast reactor for a certain time comprises irradiating said fuel assemblies inside the reactor for several hours at low power.
In a further preferred embodiment of the method for measuring a fast reactor power distribution according to the present invention, the step of shutting down the fast reactor further comprises the step of cooling the fuel assembly.
According to a further preferred embodiment of the method for measuring the fast reactor power distribution of the present invention, the step of transporting the fuel assembly to a position within the transfer chamber aligned with the collimation aperture comprises:
grabbing the fuel assembly by using an in-reactor refueling mechanism of the fast reactor;
a transfer mechanism channel for receiving the fuel assembly from the in-pile refueling mechanism by using a charging lifting mechanism of the fast reactor and conveying the fuel assembly to the transfer chamber; and
transferring the fuel assembly to a position aligned with the alignment aperture using a transfer mechanism of the transfer chamber.
In another preferred embodiment of the method for measuring a fast reactor power distribution according to the present invention, the step of measuring a parameter of gamma rays from the fuel assembly using the gamma ray detection device comprises:
Parameters of gamma rays from the fuel assembly are measured at axial and radial positions of the fuel assembly.
According to still another preferred embodiment of the method for measuring a fast reactor power distribution of the present invention, the step of measuring a parameter of gamma rays from said fuel assembly comprises:
the dead time of gamma rays, the photoelectric peak efficiency of the gamma rays and the accumulated count of the photoelectric peaks corrected by the gamma self-absorption effect are measured within a certain time.
In still another preferred embodiment of the method for measuring a power distribution of a fast reactor according to the present invention, the step of calculating the power distribution of the fast reactor from the measured parameters of the gamma rays comprises:
calculating fission reactivity at a plurality of selected locations of the core based on the parameters of the gamma rays; and
normalizing the fission reactivity at the plurality of selected locations to obtain a power distribution for the core.
According to still another preferred embodiment of the method for measuring a fast reactor power distribution of the present invention, the step of calculating fission reactivity at a plurality of selected locations of the core from the parameters of the gamma rays comprises:
the fission reactivity was calculated according to the following formula:
Wherein, FfAs the fission reaction rate at a selected location of the fuel assembly, C as the cumulative count of the measured gamma ray photoelectric peaks, IγThe absolute intensity of gamma rays with specific energy levels to be detected, epsilon is the measured photoelectric peak efficiency of the gamma rays to be detected, K is the self-absorption correction coefficient of the gamma rays to be detected in the fuel assembly, tau is the system dead time when the gamma rays emitted from the specific position of the fuel assembly are measured, lambda is the decay constant of fission products in the fuel assembly, Y is the fission yield of the fission products, N is the nuclear number of nuclides of the fission products, and T is the nuclear number of the nuclides of the fission productsMIs the irradiation time, T, of the fuel assemblyWFor the waiting time, T, from the end of irradiation to the start of measurement of the fuel assemblysThe time counted is measured.
The invention also provides a device for carrying out the method for measuring a fast reactor power distribution as described above, the device comprising:
a fuel assembly disposed in a core of the fast reactor; and
a transfer chamber in communication with a core of the fast reactor for transferring the fuel assemblies to an exterior of the core;
wherein a collimating hole penetrating the sidewall is provided in the sidewall of the transfer chamber, and a gamma ray detecting device for measuring gamma rays emitted from the fuel assembly and passing through the collimating hole is provided outside the sidewall of the transfer chamber.
In a preferred embodiment of the apparatus for performing the method for measuring a fast reactor power distribution according to the present invention, a filtering component capable of filtering low-level gamma rays is disposed at a position of the collimating hole near the gamma ray detecting device.
According to another preferred embodiment of the device for performing the method for measuring a fast reactor power distribution according to the present invention, said filter member comprises a sheet filter made of stainless steel or lead.
Compared with the fast reactor power measurement technology in the prior art, the method for measuring the fast reactor power distribution and the related equipment provided by the invention have the following beneficial effects:
(1) compared with a detection sheet activation method, the method for measuring the fast reactor power distribution and the related equipment provided by the invention are simple and convenient to operate, only through holes are required to be arranged on the side wall of the transfer chamber of the fast reactor, and special irradiation experiment assemblies and related equipment are not required to be designed and manufactured, or the original fast reactor facilities are not required to be greatly modified, so that the construction cost is low.
(2) The fast reactor power distribution measuring method occupies less time for debugging a main line, and is safe and reliable to operate by personnel.
(3) The method of the invention directly measures the fuel assembly, thus generating no additional radioactive waste, greatly reducing the radiation dose born by the staff and greatly improving the operation safety.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of the invention which refers to the accompanying drawings, and will assist in a comprehensive understanding of the invention.
FIG. 1 is a flow chart of a method for measuring fast reactor power distribution according to the present invention.
Fig. 2 is a schematic diagram of an apparatus for measuring a fast reactor power distribution according to the present invention.
It should be noted that all of the above figures are not necessarily drawn to scale, but are merely shown in schematic form not affecting the understanding of the reader.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the technical solutions of the present invention will be clearly and completely described below. It should be apparent that the described embodiments are only some of the embodiments of the present invention, and not all of them. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the invention without inventive step, are within the scope of protection of the invention.
Unless defined otherwise, technical or scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.
One aspect of the present invention provides a method for measuring fast reactor power distribution, the principles of which are described herein. The fuel assemblies of the fast reactor are irradiated at low power in the core, i.e. after a certain period of time of reaction of the fuel assemblies of the fast reactor, a certain number of fission products are produced in the fuel assemblies, the activity of which is proportional to the fission rate of the nuclear material in the fuel assemblies and to the yield of the fission products. The gamma ray detection device can be used for detecting gamma rays with specific energy emitted by specific fission products so as to obtain the fission reaction rate at a specific position of the fuel assembly, and the detection of the gamma rays with specific energy at different positions in the axial direction and different positions in the circumferential direction of the fuel assembly is used for obtaining the distribution of the fission reaction rate of the fuel assembly, so that the power distribution of the fuel assembly is obtained.
As shown in fig. 1, a flow chart of a method for measuring a fast reactor power distribution according to the present invention is shown. The method for measuring the power distribution of a fast reactor according to the present invention comprises the following steps, firstly, the arrangement of the components required for the relevant measurement is performed, and as will be explained below with reference to fig. 2, the alignment holes 14, for example in the form of through holes, are provided on the side wall 12 of the transfer chamber 10 of the fast reactor, and the alignment holes 14 penetrate through the side wall 12 of the transfer chamber 10, thereby enabling the gamma rays emitted by the fission products in the transfer chamber 10 to be transmitted from the inner side of the side wall 12 of the transfer chamber 10 to the outer side of the side wall 12, so as to facilitate the detection and measurement of the transmitted gamma rays. Further, a gamma ray detection device 16 is arranged outside the alignment hole 14 of the transfer chamber 10, that is, the gamma ray detection device 16 is arranged outside the side wall 12 of the transfer chamber 10 of the fast reactor, so that the gamma ray detection device 16 can detect the gamma rays transmitted from the alignment hole 14. After the associated hardware devices for gamma ray measurement are set, the fast reactor may be started to operate the fuel assemblies of the fast reactor for a certain period of time, such as low power operation of the fuel assemblies in the reactor for several hours, for example, 2 hours, 3 hours, 4 hours, or other time periods. And stopping the fast reactor, and detecting the gamma rays generated by the fission products after stopping the reactor, such as performing subsequent detection operations after stopping the reactor for days, for example, stopping the reactor for 2 days, 3 days, 4 days or other time periods, so that the fuel assembly of the fast reactor is sufficiently cooled. After the fuel assembly is cooled, the fuel assembly is transported to a transfer mechanism position in the transfer chamber 10 aligned with the alignment hole 14, so that the gamma rays emitted by the fission products of the fuel assembly pass through the alignment hole 14, and the parameters of the gamma rays emitted by certain fission products from the fuel assembly are measured by a gamma ray detection device 16 arranged outside the alignment hole 14. And finally, calculating the power distribution of the fast reactor according to the measured parameters of the gamma rays.
As described above, the method for measuring fast reactor power distribution according to the present invention is simple and easy compared to the detection patch activation method, and does not need to design and manufacture a dedicated irradiation experiment assembly and related equipment, thereby being low in cost. The method according to the invention occupies less time for debugging the main line, and the operation of personnel is simple and convenient. In addition, the method directly measures the fuel assembly, so that additional radioactive waste is not generated, the radiation dose born by workers is greatly reduced, and the safety is improved.
In order to prevent the low-level gamma rays from affecting the detection result of the gamma ray detection device 16, a filter member 18 capable of filtering the low-level gamma rays is provided at a position of the collimation hole 14 close to the gamma ray detection device 16. That is, the filter element 18 covering the collimating aperture 14 is provided outside the side wall 12 of the transfer chamber 10, but of course, the filter element 18 may be provided at another position of the collimating aperture 14 as long as the filter element 18 can filter out the low-level γ -rays from the fission product. Advantageously, the filter element 18 may comprise a sheet filter, such as a filter sheet, made of stainless steel or lead.
The step of transporting the fuel assemblies to the position of the alignment holes 14 in the transfer chamber 10 may include grabbing the fuel assemblies by using an in-stack refueling mechanism, that is, grabbing the fuel assemblies by using an existing refueling mechanism of a fast reactor, transferring the fuel assemblies grabbed by the refueling mechanism to a charging elevator by using the charging elevator, receiving the fuel assemblies by using the charging elevator and transporting the fuel assemblies from the reactor core to a transfer mechanism passage of the transfer chamber 10, that is, an inner cavity of the transfer chamber 10, and then transferring the fuel assemblies to the position of the transfer mechanism aligned with the alignment holes 14 by using the transfer mechanism 20 of the transfer chamber 10. The existing fuel assembly refueling and transferring mechanism in the fast reactor is utilized, so that the main structure of the fast reactor is not required to be modified, the original structure of the fast reactor is maintained, and the experiment cost is saved.
The step of detecting gamma radiation from the fuel assembly with the gamma radiation detection device 16 includes detecting gamma radiation from the fuel assembly at different axial positions and different circumferential positions of the fuel assembly. The fuel assembly can be transferred through the transfer mechanism 20 in the transfer chamber 10, so that the position of the gamma ray emitted by the fission product to be measured of the fuel assembly is aligned with the collimation hole 14 in the transfer process of the fuel assembly, the fuel assembly can be driven by utilizing the movement of the transfer mechanism 20, different positions of the axial direction of the fuel assembly sequentially pass through the collimation hole 14, and when the gamma ray at different circumferential positions of the fuel assembly is measured, different circumferential positions of the fuel assembly can be aligned with the collimation hole 14 by controlling the transfer mechanism 20 to rotate the fuel assembly, so that the gamma ray emitted at different circumferential positions of the fuel assembly can be measured.
The step of measuring the parameters of the gamma rays from the fuel assembly includes measuring an accumulated count of the gamma rays over a certain time period after dead time, a photoelectric peak efficiency of the gamma rays, and a gamma self absorption effect correction. Here, the above-mentioned parameters of the gamma rays may be measured by using the gamma ray detection device 16, which is, for example, a high purity germanium gamma spectrometer, so that the fission reaction rate of the nuclear material at a specific location of the fuel assembly may be calculated using the parameters.
The step of calculating the power distribution of the fast reactor from the measured parameters of the gamma-rays may comprise calculating the fission reactivity of the fuel assembly at a plurality of selected locations from the parameters of the gamma-rays; the fission reaction rates at the plurality of selected locations are normalized to obtain a power distribution for the fuel assembly. I.e. normalized to the overall fission reactivity of the fuel assembly by means of the local fission reactivity of the fuel assembly and thus to the power distribution of the fuel assembly.
Calculating the fission reactivity for a plurality of selected locations of the fuel assembly based on the parameters of the gamma rays comprises the steps of:
the fission reaction rate was calculated according to the following formula (1):
wherein, FfThe fission reaction rate at the selected position of the reactor core fuel assembly, C is the cumulative count of the gamma ray photoelectric peak obtained by measurement, IγThe absolute intensity of gamma rays with specific energy levels to be detected is determined, epsilon is the measured photoelectric peak efficiency of the gamma rays to be detected, K is the self-absorption correction coefficient of the gamma rays to be detected in the fuel assembly, tau is the system dead time when the gamma rays emitted from a specific position of the fuel assembly are measured, lambda is the decay constant of fission products in the fuel assembly, Y is the fission yield of the fission products, N is the nuclear number of nuclear species of the fission products, T is the nuclear number of nuclear species of the fission products MIs the irradiation time, T, of the fuel assemblyWFor the waiting time, T, from the end of irradiation to the start of measurement of the fuel assemblysThe time counted is measured.
An apparatus for measuring a fast reactor power distribution according to the present invention for performing the method for measuring a fast reactor power distribution as described above will be described with reference to fig. 2. The apparatus includes fuel assemblies disposed in a core of a fast reactor and a transfer chamber 10 communicating with the core of the fast reactor, the transfer chamber 10 for transferring the fuel assemblies to the outside of the core, where the transfer chamber 10 is generally disposed at an upper portion of the core, and the fuel assemblies are generally carried out through the transfer chamber 10 and replaced with new fuel assemblies through the transfer chamber 10 when the fuel assemblies are refilled. Further, a collimating hole 14 penetrating the side wall 12 is provided in the side wall 12 of the transfer chamber 10, and a gamma ray detecting device 16 for measuring gamma rays emitted from the fuel assembly and passing through the collimating hole 14 is provided outside the side wall 12 of the transfer chamber 10. The fission reaction rate of the fuel assembly is calculated by measuring relevant parameters of gamma rays emitted by fission products of the fuel assembly, and the power distribution of the fuel assembly of the fast reactor is obtained by normalizing the fission reaction rate at a plurality of positions of the fuel assembly.
Further, a filter member 18 capable of filtering low-level gamma rays is provided at a position of the collimating hole 14 close to the gamma ray detecting device 16. The filter element 18 may here be arranged at other positions of the collimating aperture 14, preferably outside the side wall 12 of the transfer chamber 10 as shown in fig. 2. The filter member 18 may include a sheet filter, such as a filter sheet, made of stainless steel or lead. A transfer mechanism 20 is provided inside the transfer chamber 10 for holding and transferring the fuel assemblies so that the specific locations of the fuel assemblies to be tested are aligned with the collimating holes 14 so that the gamma rays emitted from the fission products at the specific locations are received and tested by the gamma ray testing device 16.
Compared with a detection sheet activation method, the method for measuring the fast reactor power distribution and the related equipment provided by the invention are simple and convenient to operate, only through holes are required to be arranged on the side wall of the transfer chamber of the fast reactor, and special irradiation experiment assemblies and related equipment are not required to be designed and manufactured, so that the construction cost is low. The fast reactor power distribution measuring method occupies less time for debugging a main line, and is safe and reliable to operate by personnel. In addition, the method directly measures the fuel assembly, so that additional radioactive waste is not generated, the irradiation dose born by workers is greatly reduced, and the operation safety is greatly improved.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are only exemplary embodiments of the present invention and are not intended to limit the present invention, and any modifications, equivalents, improvements and the like made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (12)
1. A method for measuring fast reactor power distribution, comprising the steps of:
arranging a collimation hole on the side wall of a transfer chamber of the fast reactor, wherein the collimation hole penetrates through the side wall of the transfer chamber;
arranging a gamma ray detection device outside the side wall of the transfer chamber, wherein the gamma ray detection device is used for detecting gamma rays from the collimation hole;
operating a fuel assembly of the fast reactor for a certain time;
stopping the fast reactor;
transporting the fuel assembly to a transfer mechanism location within the transfer chamber aligned with the alignment aperture;
measuring parameters of gamma rays from the fuel assembly by using the gamma ray detection device; and
calculating the power distribution of the fast reactor according to the measured parameters of the gamma rays;
Wherein the step of calculating the power distribution of the fast reactor according to the measured parameters of the gamma rays comprises:
calculating the fission reactivity of a plurality of selected positions of the reactor core of the fast reactor according to the parameters of the gamma rays; and
normalizing the fission reactivity at the plurality of selected locations to obtain a power distribution for the core.
2. The method for measuring a fast reactor power distribution according to claim 1,
and a filtering component capable of filtering low-energy-level gamma rays is arranged at the position, close to the gamma ray detection device, of the collimation hole.
3. The method for measuring a fast reactor power distribution according to claim 2,
the filter member includes a sheet filter made of stainless steel or lead.
4. The method for measuring a fast reactor power distribution according to claim 1,
the step of operating the fuel assemblies of the fast reactor for a period of time includes irradiating the fuel assemblies within the reactor for a number of hours at low power.
5. The method for measuring a fast reactor power distribution according to claim 1,
the step of shutting down the fast reactor further comprises the step of cooling the fuel assembly.
6. The method for measuring a fast reactor power distribution according to claim 1,
the step of transporting the fuel assembly to a position within the transfer chamber aligned with the alignment aperture comprises:
grabbing the fuel assembly by using an in-reactor refueling mechanism of the fast reactor;
a transfer mechanism channel for receiving the fuel assemblies from the in-pile refueling mechanism and delivering the fuel assemblies to the transfer chamber by using a charging lifting mechanism of the fast reactor; and
transferring the fuel assembly to a position aligned with the alignment hole using a transfer mechanism of the transfer chamber.
7. The method for measuring a fast reactor power distribution according to claim 1,
the step of measuring a parameter of gamma rays from the fuel assembly using the gamma ray detection device includes:
the parameters of gamma rays from the fuel assembly are measured at different axial positions and different circumferential positions of the fuel assembly.
8. The method for measuring a fast reactor power distribution according to claim 7,
the step of measuring a parameter of gamma radiation from the fuel assembly comprises:
The dead time of gamma rays, the photoelectric peak efficiency of gamma rays and the accumulated count of photoelectric peaks are measured over a certain period of time.
9. The method for measuring fast reactor power distribution according to claim 8,
the step of calculating the fission reactivity for a plurality of selected locations of the core from the parameters of the gamma rays comprises:
the fission reactivity was calculated according to the following formula:
wherein, FfFor the fission reaction rate at a selected location of the fuel assembly, C is the cumulative count of the measured gamma ray photoelectric peaks, IγThe absolute intensity of gamma rays with specific energy levels to be detected is determined, epsilon is the measured photoelectric peak efficiency of the gamma rays to be detected, K is the self-absorption correction coefficient of the gamma rays to be detected in the fuel assembly, tau is the system dead time when the gamma rays emitted from a specific position of the fuel assembly are measured, lambda is the decay constant of fission products in the fuel assembly, Y is the fission yield of the fission products, N is the nuclear number of nuclear species of the fission products, T is the nuclear number of nuclear species of the fission productsMIs the irradiation time of the fuel assembly, TWFor the waiting time, T, of the fuel assembly from the end of irradiation to the start of measurementSThe time counted is measured.
10. An apparatus for performing the method for measuring fast reactor power distribution of claim 1, the apparatus comprising:
A fuel assembly disposed in a core of the fast reactor; and
a transfer chamber in communication with a core of the fast reactor for transferring the fuel assemblies to the exterior of the core;
characterized in that a collimating aperture is provided in the side wall of the transfer chamber through the side wall, and a gamma-ray detection device is provided outside the side wall of the transfer chamber for measuring gamma-rays emanating from the fuel assembly and passing through the collimating aperture.
11. The apparatus of claim 10,
and a filtering component capable of filtering low-energy-level gamma rays is arranged at the position, close to the gamma ray detection device, of the collimation hole.
12. The apparatus of claim 11,
the filter member includes a sheet filter made of stainless steel or lead.
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102800373A (en) * | 2012-08-17 | 2012-11-28 | 中国原子能科学研究院 | Method for scaling reactor absolute power by fission detection sheet |
| KR20140062292A (en) * | 2012-11-14 | 2014-05-23 | 한국표준과학연구원 | The measuring method of nuclear material by nuclear fission reaction by neutron and low temperature detector, and the device thereof |
| CN107230505A (en) * | 2017-06-21 | 2017-10-03 | 中国核动力研究设计院 | A kind of reactor nucleus power monitoring method and system |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP6564628B2 (en) * | 2015-06-18 | 2019-08-21 | 三菱重工業株式会社 | Apparatus and method for reconstructing axial measurements in nuclear fuel |
-
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Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102800373A (en) * | 2012-08-17 | 2012-11-28 | 中国原子能科学研究院 | Method for scaling reactor absolute power by fission detection sheet |
| KR20140062292A (en) * | 2012-11-14 | 2014-05-23 | 한국표준과학연구원 | The measuring method of nuclear material by nuclear fission reaction by neutron and low temperature detector, and the device thereof |
| CN107230505A (en) * | 2017-06-21 | 2017-10-03 | 中国核动力研究设计院 | A kind of reactor nucleus power monitoring method and system |
Non-Patent Citations (3)
| Title |
|---|
| Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores;Anatoly Kochetkov .et al;《EPJ Web of Conferences》;20171231;第1-4页 * |
| 中国实验快堆中的U-238裂变反应率测量实验研究;陈效先 等;《原子能科学技术》;20130630;第47卷;第120-122页 * |
| 中国实验快堆核反应率分布测量试验研究;范振东 等;《原子能科学技术》;20130630;第47卷;第107-110页 * |
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