CN111799006A - Method for checking software and hardware connection correctness of neutron temperature measurement channel - Google Patents
Method for checking software and hardware connection correctness of neutron temperature measurement channel Download PDFInfo
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- CN111799006A CN111799006A CN202010503522.9A CN202010503522A CN111799006A CN 111799006 A CN111799006 A CN 111799006A CN 202010503522 A CN202010503522 A CN 202010503522A CN 111799006 A CN111799006 A CN 111799006A
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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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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
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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 relates to the technical field of nuclear power station reactor core nuclear measurement systems, in particular to a method for checking the connection correctness of software and hardware of a neutron temperature measurement channel. The checking method comprises the following steps: adjusting the power of the unit and the rod position of a control rod; selecting n control rods as an execution group; inserting an ith control rod downwards, and measuring a power peak factor of a region around the control rod before the control rod is inserted; inserting the control rods downwards to the bottom of the reactor core, and measuring the power peak factors of the control rods in the surrounding area after rod insertion; lifting the control rod to an initial height; calculating the relative power change value of a neutron temperature measurement channel in the area around the control rod; if the i is not equal to i +1, the step is repeated; and if so, judging the correctness of the software and hardware connection of the neutron temperature measurement channel at the corresponding position according to the relative power change value. The checking method can quickly and accurately judge the correctness of the connection of software and hardware of the neutron temperature measuring channel, and is safe and reliable.
Description
Technical Field
The invention relates to the technical field of nuclear power station reactor core nuclear measurement systems, in particular to a method for checking the connection correctness of software and hardware of a neutron temperature measurement channel.
Background
The nuclear power unit uses a reactor core measuring system to monitor signal parameters such as reactor core neutron flux distribution, temperature and water level in the reactor core in real time during the operation of the reactor, and generates corresponding protection signals under the operation, transient and accident conditions of the unit so as to achieve the aim of ensuring the safe and economic operation of the reactor. Reactor core measuring systems are designed and installed in Hualong I nuclear power units and Russian VVER nuclear power units which are independently designed and built in China.
One of the core components of the core measurement system is a neutron temperature measurement channel, which is mounted in the in-core fuel assembly. And measuring elements such as a self-powered detector and a thermocouple are arranged on the neutron temperature measuring channel, and a current signal formed by the self-powered detector and an electromotive force signal formed by the thermocouple are transmitted to a computing terminal through a transmission cable for processing, so that parameters such as neutron flux distribution, temperature and the like of the reactor core are monitored.
As dozens of beam neutron temperature measurement channels are installed in the reactor core, the transmission cable needs to be disconnected after the cover is overhauled by the unit each time, and the condition that the transmission cable is connected in a wrong way can exist in reconnection, so that the software and hardware of the neutron temperature measurement channels are connected incorrectly, the neutron flux distribution, the temperature and other parameters of the reactor core are measured incorrectly, and the monitoring and protection functions of the reactor core are invalid. The hard-wired communication inspection methods currently adopted by some power stations are time-consuming and labor-consuming, and have certain radiation dose and foreign matter introduction risks due to operation above the reactor.
Disclosure of Invention
The technical problem to be solved by the invention is as follows: the method for checking the connection correctness of the software and the hardware of the neutron temperature measurement channel can quickly and accurately judge the connection correctness of the software and the hardware of the neutron temperature measurement channel, and is safe and reliable.
The invention provides a method for checking the connection correctness of software and hardware of a neutron temperature measurement channel, which comprises the following steps:
step S1: adjusting the power of the unit to 40-60% of rated level, and the rod position of the control rod is 70-75% of the height of the reactor core; selecting n control rods as an execution group; n is a natural number;
step S2: the method for monitoring the power peak factor change condition of the area around the control rod in the process of inserting the ith control rod comprises the following steps: determining the peak power factor Kq of the area around the control rod before rod insertioni(ii) a I is more than or equal to 1 and less than or equal to n; when in the first calculation, i is 1, and when in the subsequent calculation, i is updated iteratively according to the subsequent calculation process;
when the control rod is inserted downwards to the position 50% of the height of the reactor core, the control rod stays for 1-2 minutes, when the power distribution is not changed any more, the control rod is continuously inserted downwards to the bottom of the reactor core and stays for 1-2 minutes at the bottom of the reactor core, and after the bottom of the reactor core is measured, the power peak factor Kq of the area around the control rod after the rod is inserted is measuredi’；
Step S3: lifting the control rods to an initial height to stabilize reactor core parameters;
step S4: calculating the relative power change value of the neutron temperature measurement channel in the area around the control rod, wherein the calculation formula is as follows: Δ Kqi＝(Kqi’-Kqi)/Kqi；
Step S5: if i is equal to i +1, determining whether i > n is true, and if not, repeating steps S2-S5;
if yes, go to step S6;
step S6: and judging the correctness of the software and hardware connection of the neutron temperature measurement channel at the corresponding position according to the relative power change value.
Preferably, the judging the correctness of the software and hardware connection of the neutron temperature measurement channel comprises:
said Δ KqiThe maximum value of the absolute value appears in the fuel assembly corresponding to the lower inserted control rod;
taking the fuel assembly corresponding to the lower inserted control rod as a center, and the relative change of the relative power change value of the fuel assembly farther away from the center is smaller;
calculating an asymmetry value delta of a power variation value of a neutron temperature measurement channel at a symmetric position of a reactor core, wherein the calculation formula is as follows:
the delta is not more than 10%;
if the conditions are met, the software and hardware connection of the neutron temperature measurement channel at the position is normal.
Preferably, n is 6.
Preferably, n control rods in symmetrical positions are selected as the actuating group.
Preferably, in step S1, the set power is adjusted to 50% of the rated level.
Preferably, in the step S1, the control rods have rod positions at 75% of the core height.
Preferably, in step S2, the power crest factor variation of the area around the control rods is monitored, and the core power distribution distortion is continuously observed to ensure safe operation of the reactor.
Preferably, step S1 is preceded by: checking the working states of the reactor control rod system and the reactor core measuring system and the normality of the reactor core power distribution parameter display.
Compared with the prior art, the method for checking the software and hardware connection correctness of the neutron temperature measurement channel is used for checking the software and hardware connection correctness of the nuclear power unit provided with the neutron temperature measurement channel, can quickly and accurately judge the software and hardware connection correctness of the neutron temperature measurement channel, improves the checking reliability, optimizes the overhaul period of the nuclear power unit and reduces manual operation.
Drawings
FIG. 1 is a schematic flow chart of the method for checking the correctness of the software and hardware connection of the seed temperature measurement channel according to the present invention;
FIG. 2 is a diagram showing the arrangement of a nuclear power plant control cluster according to embodiment 1 of the present invention;
FIG. 3 is a view showing the arrangement of neutron temperature measurement channels of the nuclear power plant in embodiment 1 of the present invention;
FIG. 4 is a graph showing the results of an asymmetry calculation of the power change Δ Kqi of the neutron temperature measurement channel in a symmetric position;
in FIGS. 2 and 3, reference numerals 01 to 42 denote core coordinate positions.
Detailed Description
For a further understanding of the invention, embodiments of the invention are described below in conjunction with the examples, but it should be understood that these descriptions are included merely to further illustrate features and advantages of the invention, and are not intended to limit the invention.
The embodiment of the invention discloses a method for checking the connection correctness of software and hardware of a neutron temperature measurement channel, which comprises the following steps:
step S1: adjusting the power of the unit to 40-60% of rated level, and the rod position of the control rod is 70-75% of the height of the reactor core; selecting n control rods as an execution group; n is a natural number;
step S2: the method for monitoring the power peak factor change condition of the area around the control rod in the process of inserting the ith control rod comprises the following steps: determining the peak power factor Kq of the area around the control rod before rod insertioni(ii) a I is more than or equal to 1 and less than or equal to n; when in the first calculation, i is 1, and when in the subsequent calculation, i is updated iteratively according to the subsequent calculation process;
when the control rod is inserted downwards to the position 50% of the height of the reactor core, the control rod stays for 1-2 minutes, when the power distribution is not changed any more, the control rod is continuously inserted downwards to the bottom of the reactor core and stays for 1-2 minutes at the bottom of the reactor core, and after the bottom of the reactor core is measured, the power peak factor Kq of the area around the control rod after the rod is inserted is measuredi’；
Step S3: lifting the control rods to an initial height to stabilize reactor core parameters;
step S4: calculating the relative power change value of the neutron temperature measurement channel in the area around the control rod, wherein the calculation formula is as follows: Δ Kqi＝(Kqi’-Kqi)/Kqi；
Step S5: if i is equal to i +1, determining whether i > n is true, and if not, repeating steps S2-S5;
if yes, go to step S6;
step S6: and judging the correctness of the software and hardware connection of the neutron temperature measurement channel at the corresponding position according to the relative power change value.
And the neutron temperature measuring channel comprises a self-powered detector, wherein an absorption material capable of generating nuclear reaction with neutrons exists in the self-powered detector, and is finally transmitted to a computer terminal for processing in the form of current, so that the magnitude of the current generated by the self-powered detector is in direct proportion to the magnitude of neutron flux near the position of the self-powered detector. By utilizing the principle, the seed flux at a certain position of the reactor core is reduced by inserting a control rod at the position downwards, so that the current detected at the position in the computer terminal and the power level after processing are reduced, and whether the neutron temperature measuring channel is connected wrongly or not is judged through phenomenon analysis. The operation is continuously executed, and the correctness of software and hardware connection of the neutron temperature measurement channel in the full reactor core can be judged.
The method for checking the software and hardware connection correctness of the sub-temperature measurement channel is described in detail according to the following steps:
step S1: adjusting the power of the unit to 40-60% of rated level, and the rod position of the control rod is 70-75% of the height of the reactor core; selecting n control rods as an actuating group.
Preferably, the operating conditions of the reactor control rod system, the core measurement system and the normality of the core power distribution parameter display are first checked. And if the working states of the reactor control rod system and the reactor core measuring system and the reactor core power distribution parameters are displayed normally, selecting an initial state.
Considering that the power distribution of the core can be distorted after the single bundle of control rods are inserted downwards, the power distribution of partial positions will be increased, and therefore, the nuclear power of the unit is adjusted to be lower than a safety level before the inspection method is implemented. The initial state specifically comprises: the power of the unit is adjusted to 40-60% of rated level, and the rod position of the control rod is 70-75% of the height of the reactor core.
Preferably, the power of the unit is adjusted to 50% of the rated level, and the rods of the control rods are positioned at 75% of the height of the core.
Selecting n control rods as an execution group, wherein n is a natural number. The control rods as the actuating group are selected according to the position of the neutron temperature measurement channel, and preferably n is 6. Preferably, n control rods in symmetrical positions are selected as the actuating group.
Step S2: the method for monitoring the power peak factor change condition of the area around the control rod in the process of inserting the ith control rod comprises the following steps: determining the peak power factor Kq of the area around the control rod before rod insertioni(ii) a I is more than or equal to 1 and less than or equal to n; when in the first calculation, i is 1, and when in the subsequent calculation, i is updated iteratively according to the subsequent calculation process;
when the control rod is inserted downwards to the position 50% of the height of the reactor core, the control rod stays for 1-2 minutes, when the power distribution is not changed any more, the control rod is continuously inserted downwards to the bottom of the reactor core and stays for 1-2 minutes at the bottom of the reactor core, and after the bottom of the reactor core is measured, the power peak factor Kq of the area around the control rod after the rod is inserted is measuredi’。
The control rod surrounding area means: the area range formed by two fuel assemblies adjacent to a control rod in all directions by taking the control rod as a center.
Preferably, in step S2, the power crest factor variation of the area around the control rods is monitored, and the core power distribution distortion is continuously observed to ensure safe operation of the reactor.
Step S3: and lifting the control rods to the initial height to stabilize reactor core parameters.
This step allows the core to maintain normal operation in order to provide initial conditions for the next test.
Step S4: calculating the relative power change value of the neutron temperature measurement channel in the area around the control rod, wherein the calculation formula is as follows: Δ Kqi＝(Kqi’-Kqi)/Kqi。
Step S5: if i is equal to i +1, determining whether i > n is true, and if not, repeating steps S2-S5;
if true, go to step S6.
And (3) repeating the steps until the relative power change of the neutron temperature measurement channels in the surrounding area of all control rods of the execution group is obtained, because the software and hardware connection condition of the plurality of neutron temperature measurement channels in the reactor core needs to be judged.
Step S6: and judging the correctness of the software and hardware connection of the neutron temperature measurement channel at the corresponding position according to the relative power change value.
The judgment of the correctness of the connection of software and hardware of the neutron temperature measurement channel comprises the following steps:
said Δ KqiThe maximum value of the absolute value appears in the fuel assembly corresponding to the lower inserted control rod;
taking the fuel assembly corresponding to the lower inserted control rod as a center, and the relative change of the relative power change value of the fuel assembly farther away from the center is smaller;
calculating an asymmetry value delta of a power variation value of a neutron temperature measurement channel at a symmetric position of a reactor core, wherein the calculation formula is as follows: (ii) a The delta is not more than 10%;
if the conditions are met, the software and hardware connection of the neutron temperature measurement channel at the position is normal.
For further understanding of the present invention, the following provides a detailed description of the method for checking the correctness of the hardware and software connections of the neutron temperature measurement channel, which is provided by the present invention, with reference to the following embodiments, and the scope of the present invention is not limited by the following embodiments.
Example 1
(1) And checking that the working states of the reactor control rod system and the reactor core measuring system and the power distribution parameter display of the reactor core are normal.
And selecting an initial state, and adjusting the power of the unit to 50% of a rated level, wherein the rod position of the control rod is 75% of the height of the reactor core.
(2) Determining a group of drop-in control bundles: the selected pressurized water reactor unit is a hexagonal reactor, reactor core fuel assemblies are symmetrically loaded according to 1/6, the selected lower inserted control rod group is symmetrically selected according to 1/6, the reactor core coordinate positions 04-29, 10-23, 06-35, 12-29, 06-23 and 10-35 in the figure 2 are selected as execution groups, and a proper control rod group is selected according to the position of a neutron temperature measurement channel.
A first control rod is inserted at a certain position of the reactor core. As shown in FIG. 2, 04-29 is selected, the change of the power peak factor near 04-29 is monitored by using the computer terminal screen in the reactor core measuring system during the process of inserting the control rod at the position, and the power sub factor Kq near the control rod at the position 04-29 before inserting is recorded1(ii) a And meanwhile, the power distribution distortion condition of the reactor core is continuously observed to ensure the safe operation of the reactor. The reactor core stays for 1 to 2 minutes when being inserted to the position of 50 percent of the height of the reactor core, and is continuously inserted to the bottom of the reactor core when the power distribution is not changed; and (3) staying at the bottom of the reactor core for 1-2 minutes, recording relevant data when relevant parameters are not changed any more, and recording the power peak factor after the control rod at the 04-29 position is inserted to the bottom of the reactor core.
(3) And lifting the control rods at the 04-29 positions to the initial height to stabilize the reactor core parameters.
(4) Calculating the relative power change delta Kq of the neutron temperature measurement channel at the position near 04-291The specific neutron temperature measurement channel is shown in fig. 3.
The calculation formula of the relative power change value is as follows: Δ Kq1＝(Kq1’-Kq1)/Kq1。
(5) And (4) repeating the steps (2) to (4) to respectively obtain the relative power changes of the neutron temperature measurement channels in the areas around the positions of 0-23, 06-35, 12-29, 06-23 and 10-35.
(6) And judging the correctness of the software and hardware connection of the neutron temperature measurement channel at the corresponding position according to the relative power change value. The judgment standard is as follows:
the maximum value of the absolute value of the delta Kqi appears in the fuel assembly corresponding to the lower inserted control rod;
taking the fuel assembly corresponding to the lower inserted control rod as a center, and the relative change of the relative power change value of the fuel assembly farther away from the center is smaller;
calculating an asymmetry value delta of the power change value of the seed temperature measurement channel at the symmetric position of the reactor core, wherein the calculation formula is as follows:
the delta is not more than 10%;
if the conditions are met, the software and hardware connection of the neutron temperature measurement channel at the position is normal.
The relative power variation values of the neutron temperature measurement channels in this embodiment are shown in fig. 4. As can be seen from fig. 4, the neutron temperature measurement channels at the above 6 positions have correct hardware and software connections.
The above description of the embodiments is only intended to facilitate the understanding of the method of the invention and its core idea. It should be noted that, for those skilled in the art, it is possible to make various improvements and modifications to the present invention without departing from the principle of the present invention, and those improvements and modifications also fall within the scope of the claims of the present invention.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (8)
1. A method for checking the correctness of software and hardware connection of a neutron temperature measurement channel is characterized by comprising the following steps:
step S1: adjusting the power of the unit to 40-60% of rated level, and the rod position of the control rod is 70-75% of the height of the reactor core; selecting n control rods as an execution group; n is a natural number;
step S2: the method for monitoring the power peak factor change condition of the area around the control rod in the process of inserting the ith control rod comprises the following steps: measuring the circumference of the control rodPeak power factor Kq of region before plungeri(ii) a I is more than or equal to 1 and less than or equal to n; when in the first calculation, i is 1, and when in the subsequent calculation, i is updated iteratively according to the subsequent calculation process;
when the control rod is inserted downwards to the position 50% of the height of the reactor core, the control rod stays for 1-2 minutes, when the power distribution is not changed any more, the control rod is continuously inserted downwards to the bottom of the reactor core and stays for 1-2 minutes at the bottom of the reactor core, and after the bottom of the reactor core is measured, the power peak factor Kq of the area around the control rod after the rod is inserted is measuredi’；
Step S3: lifting the control rods to an initial height to stabilize reactor core parameters;
step S4: calculating the relative power change value of the neutron temperature measurement channel in the area around the control rod, wherein the calculation formula is as follows: Δ Kqi＝(Kqi’-Kqi)/Kqi；
Step S5: if i is equal to i +1, determining whether i > n is true, and if not, repeating steps S2-S5;
if yes, go to step S6;
step S6: and judging the correctness of the software and hardware connection of the neutron temperature measurement channel at the corresponding position according to the relative power change value.
2. The method for checking the correctness of the software and hardware connection of the neutron temperature measurement channel according to claim 1, wherein the step of judging the correctness of the software and hardware connection of the neutron temperature measurement channel comprises the following steps:
said Δ KqiThe maximum value of the absolute value appears in the fuel assembly corresponding to the lower inserted control rod;
taking the fuel assembly corresponding to the lower inserted control rod as a center, and the relative change of the relative power change value of the fuel assembly farther away from the center is smaller;
calculating an asymmetry value delta of a power variation value of a neutron temperature measurement channel at a symmetric position of a reactor core, wherein the calculation formula is as follows:
the delta is not more than 10%;
if the conditions are met, the software and hardware connection of the neutron temperature measurement channel at the position is normal.
3. The method for checking software and hardware connection correctness of a neutron temperature measurement channel according to claim 1, wherein n is 6.
4. The method for checking the correctness of the software and hardware connections of the neutron temperature measurement channel according to claim 1 or 2, characterized in that n control rods with symmetrical positions are selected as an execution group.
5. The method for checking software and hardware connection correctness of a neutron temperature measurement channel according to claim 1, wherein in the step S1, the power of the set is adjusted to 50% of the rated level.
6. The method for checking software and hardware connection correctness of a neutron temperature measurement channel according to claim 1, wherein in the step S1, the rod position of the control rod is at 75% of the core height.
7. The method for checking software and hardware connection correctness of a neutron temperature measurement channel according to claim 1, wherein in the step S2, the power peak factor variation of the area around the control rod is monitored, and the core power distribution distortion is continuously observed to ensure the safe operation of the reactor.
8. The method for checking software and hardware connection correctness of a neutron temperature measurement channel according to claim 1, wherein before the step S1, the method further comprises: checking the working states of the reactor control rod system and the reactor core measuring system and the normality of the reactor core power distribution parameter display.
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