CN104347129B - The fuel assembly handling method of pressurized-water reactor nuclear power plant - Google Patents
The fuel assembly handling method of pressurized-water reactor nuclear power plant Download PDFInfo
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- CN104347129B CN104347129B CN201310327241.2A CN201310327241A CN104347129B CN 104347129 B CN104347129 B CN 104347129B CN 201310327241 A CN201310327241 A CN 201310327241A CN 104347129 B CN104347129 B CN 104347129B
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- refueling machine
- control system
- fuel assembly
- reactor core
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/207—Assembling, maintenance or repair of reactor components
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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
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of fuel assembly stowage of pressurized-water reactor nuclear power plant, including：Control system drives the cart and dolly of refueling machine to run to the predetermined full offset position of target simultaneously；Control system drives the main lifting of refueling machine to drop to the first height；Control system drives cart and trolley travelling to target location；Control system drives main lifting to drop to reactor core bottom.Compared with prior art, the fuel assembly stowage of pressurized-water reactor nuclear power plant of the invention use only a bias mode on the premise of fuel assembly safety is ensured（Full bias mode）, the secondary bias mode of " full biasing+half biases " employed in conventional load process is compared, and is improve the efficiency of reloading of refueling machine, is shortened overhaul critical path time, so that significant economic benefit is brought to nuclear power station.The present invention discloses a kind of fuel assembly discharging method of pressurized-water reactor nuclear power plant.
Description
Technical field
The present invention relates to the handling technique field of pressurized-water reactor nuclear power plant fuel assembly, relates more specifically to a kind of presurized water reactor core
The fuel assembly handling method in power station.
Background technology
The loading and unloading of pressurized-water reactor nuclear power plant fuel assembly is mainly completed by refueling machine, and handling fuel assembly process is nuclear power
Stand one of critical path during overhaul.How on the premise of nuclear fuel assembly safety is ensured, handling are completed with the most short time
Work direct relation overhaul critical path time, so as to affect the benefit of nuclear power station.
In order to ensure the safety of fuel assembly, cause mutually to scratch because distance is too near in preventing cargo handling process, refueling machine
Typically can be by the way of biasing, i.e., refueling machine leaves one segment distance of target location when fuel assembly is plugged.And according to distance
Difference, bias mode is divided into two kinds of full biasing and half biasing（As shown in Figure 1）.
Fig. 2 is refer to, during existing loading and unloading, by taking charging process as an example, its idiographic flow is as follows：
Whether S101, need to be biased according to the current position judgment of refueling machine, if so, then performs S102, conversely, then
Perform S106.Specifically, as shown in Figures 3 and 4, refueling machine is run on reactor core track above and is connected with control system, main
To be made up of cart, dolly and three part of main lifting, reactor core is located at the back upper place of refueling machine.Wherein, before and after cart is responsible for（X side
To）Motion, dolly be responsible for left and right（Y-direction）Motion, main lifting is then responsible for upper and lower（Z-direction）Motion.The control system
Built with a set of Programmable Logic Controller, the control software of operation refueling machine in which.During work, control system is big by being loaded into
Three encoders in car, dolly and main lifting obtain position signalling, and the current location of real-time judge refueling machine in real time, according to
The current location judges whether that needs are biased, and the follow-up operation direction of refueling machine various pieces is by control system control
System, until completing the work that entirely feeds.
S102, the cart and dolly of refueling machine are run simultaneously to full offset position.
S103, main lifting drop to 7900mm height, and the whole height of reactor core is about 8700mm.
S104, the cart and dolly of refueling machine are run simultaneously to half offset position.
S105, main lifting drop to 8700mm height.
S106, the cart and dolly of refueling machine are run to target screen work simultaneously.
S107, main lifting drop to reactor core bottom, and up to discharge, fuel assembly is seated on target screen work.
To sum up, existing refueling machine uses the secondary bias mode of " full biasing+half biases "（As shown in Figure 5）, lead
The inefficiency of reloading of refueling machine being caused, overhaul critical path time is extended, so as to have impact on nuclear power station benefit.
In addition, the control software loaded in control system is when judging whether to need to be biased, its idiographic flow
It is：Reactor core assembly is changed into into 289 digital, each unique numberings of fuel assembly correspondence of 17*17, is formed as shown in Figure 6
Reactor core pointer figure.When refueling machine is moved in heap in-core, control system can be encoded according to three in cart, dolly and main lifting
Device obtains the current location that position signalling learns refueling machine in real time, learns the present bit of refueling machine afterwards according to the reactor core pointer figure
Put and belong to which fuel assembly numbering, finally whether load further according to fuel assembly around the affiliated numbering learnt, enter
Can one step judge meet bias condition and determine biased direction.That is, sentencing for condition is biased by the way of pointer poll
The determination of disconnected and biased direction.When using pointer polling mode, in order to which combustion the current location for determining refueling machine belongs to
Material component numerals, are required for facilitating whole reactor core pointer figure every time, extremely inefficient, and do not carry out framework optimization, it is impossible to meet real
When property requires also there is the possibility of erroneous judgement.
Equally, in discharge process, refueling machine still uses the secondary bias mode of " full biasing+half biases ", leads
The inefficiency of reloading of refueling machine being caused, overhaul critical path time is extended, so as to have impact on nuclear power station benefit.And in judgement be
It is not no when needing to be biased, remain using above-mentioned pointer polling mode.
Therefore, it is necessary to provide a kind of improved fuel assembly handling method to overcome drawbacks described above.
The content of the invention
It is an object of the invention to provide a kind of handling method of pressurized-water reactor nuclear power plant fuel, to ensure fuel assembly safety
On the premise of, the efficiency of reloading of refueling machine is improved, and shortens overhaul critical path time, so that significant economy is brought to nuclear power station
Benefit.
For achieving the above object, the invention provides a kind of fuel assembly stowage of pressurized-water reactor nuclear power plant, including：
（1）Control system drives the cart and dolly of refueling machine to run to target predetermined bias position simultaneously；
（2）The control system drives the main lifting of the refueling machine to drop to the first height；
（3）The control system drives the cart and trolley travelling to target location；
（4）The control system drives the main lifting to drop to reactor core bottom.
Compared with prior art, the fuel assembly stowage of pressurized-water reactor nuclear power plant of the invention, now by cart and dolly
Run to the predetermined full offset position of target simultaneously, then main lifting is dropped to into the first height（I.e. at the top of reactor core
At 8700mm）, afterwards by cart and trolley travelling to target location, main lifting is dropped to into reactor core bottom with complete finally
Into the loading process of fuel assembly；That is, the stowage on the premise of fuel assembly safety is ensured use only and once bias
Mode（Full bias mode）, the secondary bias mode of " full biasing+half biases " employed in conventional load process is compared, is improved
The efficiency of reloading of refueling machine, shortens overhaul critical path time, so as to bring significant economic benefit to nuclear power station.
It is preferred that carrying out step（1）Also include before：
Biasing is judged whether to according to the current location of the refueling machine, step is carried out according to judged result（1）Or step
Suddenly（3）.
Specifically, " judge whether to biasing according to the current location of the refueling machine " to specifically include：
Reactor core two-dimensional array figure is set up with the direction of motion dimension of the cart and the dolly；
The current location of the refueling machine is converted to into the position in the reactor core two-dimensional array figure；
Biasing and biased direction are judged whether to using nine grids model.
It is preferred that also including before carrying out " judge whether to bias using nine grids model and determine biased direction "：
Judge whether the target location is legal.
Specifically, first height is at the top of reactor core at 8.7 meters.
Correspondingly, present invention also offers a kind of fuel assembly discharging method of pressurized-water reactor nuclear power plant, including：
（1）Control system drives the cart and dolly of refueling machine to run to target location simultaneously；
（2）The control system drives the main lifting of the refueling machine to rise to the first height；
（3）The control system drives the cart and dolly to run to the predetermined full offset position of target simultaneously；
（4）The control system drives the main lifting to rise at the top of reactor core.
Compared with prior art, the fuel assembly discharging method of pressurized-water reactor nuclear power plant of the present invention, first will be cart and dolly same
Shi Yunhang rises to the first height to target location, then by main lifting（I.e. at the 8700mm at the top of reactor core）, it
Afterwards main lifting finally is risen at the top of reactor core to complete fuel stack by cart and trolley travelling to the predetermined offset position of target
The uninstall process of part；That is, the discharging method use only a bias mode on the premise of fuel assembly safety is ensured（Entirely
Bias mode）, the secondary bias mode of " full biasing+half biases " employed in traditional uninstall process is compared, is improve and is reloaded
The efficiency of reloading of machine, shortens overhaul critical path time, so as to bring significant economic benefit to nuclear power station.
It is preferred that carrying out step（1）Also include before：
Biasing is judged whether to according to the current location of the refueling machine.
Specifically, " judge whether to biasing according to the current location of the refueling machine " to specifically include：
Reactor core two-dimensional array figure is set up with the direction of motion dimension of the cart and the dolly；
The current location of the refueling machine is converted to into the position in the reactor core two-dimensional array figure；
Judge whether to bias using nine grids model and determine biased direction.
It is preferred that also including before carrying out " judge whether to bias using nine grids model and determine biased direction "：
Judge whether the target location is legal.
Specifically, first height is at the top of reactor core at 8.7 meters.
By description below and accompanying drawing is combined, the present invention will become more fully apparent, these accompanying drawings are used to explain the present invention
Embodiment.
Description of the drawings
Schematic diagrams of the Fig. 1 for bias mode.
Fig. 2 is the charging flow chart of existing fuel assembly.
Fig. 3 is the schematic diagram of refueling machine and reactor core.
Schematic diagrams of the Fig. 4 for refueling machine control system.
Fig. 5 is the secondary biasing schematic diagram of charging flow chart described in Fig. 2.
Fig. 6 is reactor core pointer figure.
Fig. 7 is the flow chart of one embodiment of fuel assembly stowage of present invention reaction reactor of nuclear power plant.
Once biasing schematic diagrams of the Fig. 8 for stowage flow chart described in Fig. 7.
Sub-process figures of the Fig. 9 for step S201 shown in Fig. 7.
Reactor core two-dimensional array figures of the Figure 10 for step S2011 shown in Fig. 9.
Figure 11 is two-dimensional array latitude coordinates schematic diagram.
Figure 12 is nine grids model schematic.
Flow charts of the Figure 13 for target location validity judgement.
9 kind legal situation schematic diagrams of the Figure 14 for target location.
Figure 15 is the flow chart for determining biased direction according to Figure 12.
Figure 16 be 4 kinds meet biasing reload condition situation the schematic diagram that reloads.
Figure 17 is the flow chart of one embodiment of fuel assembly discharging method of present invention reaction reactor of nuclear power plant.
Specific embodiment
With reference now to Description of Drawings embodiments of the invention, the element numbers being similar in accompanying drawing represent similar element.
Fig. 7 is refer to, the fuel assembly stowage of pressurized-water reactor nuclear power plant of the present invention is comprised the following steps：
S201, judges whether to biasing according to the current location of refueling machine, if so, then carries out S202, conversely, then carrying out
S204；
S202, control system drive cart and dolly to run to the predetermined full offset position of target simultaneously；As shown in Figure 8
Full offset position；
S203, control system drive main lifting to drop to the first height, i.e., at the top of reactor core 8.7 meters；
S204, control system drive cart and dolly to run to target location simultaneously；
S205, control system drive main lifting to drop to reactor core bottom, and up to discharge, fuel assembly is seated target
On screen work.
It should be noted that step S201, S204 and S205 are in the case where S201 judges to be biased,
The loading of the fuel assembly completed using straight cutting mode.
From the above description and Fig. 8 can be seen that in the loading process of fuel assembly, before fuel assembly safety is ensured
Put, use only a bias mode（Full bias mode）, compare " the full biasing+partly inclined employed in conventional load process
Put " secondary bias mode, improve the efficiency of reloading of refueling machine, shorten overhaul critical path time, so as to give nuclear power station
Bring significant economic benefit.
Specifically, as shown in figure 9, step S201 is specifically included：
S2011, sets up reactor core two-dimensional array figure with the direction of motion dimension of cart and dolly；Specifically, using 17*17's
Two-dimensional array replaces traditional reactor core pointer figure, and X is the direction of motion dimension of cart, covers 01-15 encoding pack of reactor core, and Y is
The direction of motion dimension of dolly, covers reactor core A-R encoding packs, Array【X, Y】Reactor core single subassembly is represented, is built
As shown in Figure 10, the white portion in figure represents reactor core to vertical reactor core two-dimensional array figure；
The current location of refueling machine is converted to the position in reactor core two-dimensional array figure by S2012；Specifically, it is loaded into and changes
Three encoders of the cart, dolly and main lifting of material machine obtain the X-direction of refueling machine in real time（The cart direction of motion）, Y-direction
（Moving of car direction）And Z-direction（Main lifter motion direction）Positional information, control system judged according to three positional informationes
Go out the current location of refueling machine, the current location of refueling machine is converted to the position in reactor core two-dimensional array figure and specifically adopts following
Coordinate system and computing formula：
As shown in figure 11, using tumbler be located position as origin, the center point coordinate of reactor core is（X0, y0）, reload
The current position coordinates of machine are（X, y）, and core grid at intervals of L, then the starting point coordinate of the two-dimensional array shown in Figure 10 is
（X0+8.5*L, y0+8.5*L）, two-dimensional array Array is obtained further according to dimension computing formula【X, Y】Dimension, finally according to institute
The dimension tried to achieve simultaneously just can learn the current location of refueling machine position in Fig. 10 with reference to reactor core two-dimensional array figure, that is, complete
The conversion of position of the current location of refueling machine in reactor core two-dimensional array figure, wherein, dimension computing formula is：
X=INT（（x0-x）/L+8.5）
Y=INT（（y0-y）/L+8.5）
Wherein INT is represented and is rounded；
S2013, judges whether target location is legal, if so, then carries out step S2014, conversely, then terminating；Specifically, root
Specify that at least adjacent two sides of reactor core inner assembly is supported according to fuel assembly technical specification（Can be coaming plate or another group
Part）, to prevent component from toppling over because of crank, therefore must be to the legal of target location before refueling machine operation nuclear fuel assembly
Property is judged.Assume target location two-dimensional array dimension be【X, Y】, for the ease of analysis, by group around target location
Part is numbered, and as shown in figure 12, carries out with reference to the target location validity judgement flow process of the nine grids model and Figure 13 of Figure 12
Analysis judges, has obtained the legal effective situation in as shown in figure 14 9 kind target location, be further advanced by 9 kinds of conjunctions in Figure 14
The induction and conclusion of method situation, it can be deduced that conclusion：Whether legal target location be related to four positions such as the 1st, 3,5,7, i.e.,
In this four positions, at least 2 adjacent positions have loaded fuel assembly；
S2014, judges whether to bias using nine grids model and determines biased direction；Specifically, in order to avoid combustion
Material component occurs scratching in relative motion, it is super underload situations such as, refueling machine operates nuclear fuel assembly using bias mode, therefore
Not only require that target location is legal, while require that three adjacent positions not yet load fuel assembly around target location, in Figure 14
The legal situation in 9 kinds of target locations in, only tetra- kinds of situations of a-d meet bias condition, in conjunction with Figure 12 and Figure 15 understand, when
In screen work 2, screen work 1 and screen work 3 during equal unloaded fuel assembly, it is determined that biased direction is upper left, when screen work 4, screen work 3 are passed
In frame 5 during equal unloaded fuel assembly, it is determined that biased direction is upper right, when equal unloaded combustion in screen work 6, screen work 5 and screen work 7
During material component, it is determined that biased direction is bottom right, when equal unloaded fuel assembly in screen work 8, screen work 7 and screen work 1, it is determined that
Biased direction is lower-left, and four kinds of schematic diagrams that reload for meeting bias condition situation are as shown in figure 16.
From the above, it can be seen that when judging whether that needs are biased and determine biased direction, the present invention is adopted
Method based on two-dimensional array technology substitutes traditional pointer polling mode, improves efficiency, and optimizes framework, meets
The requirement of real-time, and there is no the possibility of erroneous judgement.
Correspondingly, present invention also offers a kind of fuel assembly discharging method of pressurized-water reactor nuclear power plant, as shown in figure 17, its
Specifically include following steps：
S301, judges whether to biasing according to the current location of refueling machine, if so, then carries out S302, conversely, then carrying out
S306；
S302, control system drive cart and dolly to run to target location simultaneously；
S303, control system drive main lifting to rise to the first height；At 8700mm as shown in Figure 8；
S304, control system drive cart and dolly to run to the predetermined full offset position of target simultaneously；As shown in Figure 8
Full offset position；
S305, control system drive main lifting to rise at the top of reactor core, complete the unloading of fuel assembly；
S306, control system drive cart and dolly to run to target location simultaneously；
S307, control system drive main lifting to rise at the top of reactor core, complete the unloading of fuel assembly.
It should be noted that step S301, S306 and S307 are in the case where S301 judges to be biased,
The unloading of the fuel assembly completed using straight cutting mode.
From the above description and Fig. 8 can be seen that in the uninstall process of fuel assembly, before fuel assembly safety is ensured
Put, use only a bias mode（Full bias mode）, compare " the full biasing+partly inclined employed in conventional load process
Put " secondary bias mode, improve the efficiency of reloading of refueling machine, shorten overhaul critical path time, so as to give nuclear power station
Bring significant economic benefit.
It should be noted that in the discharging method of fuel assembly, its " according to the current location of refueling machine judge whether into
The concrete judgement step of row biasing " is identical with the judgement step in the stowage of fuel assembly, therefore will not be described here.
Above in association with most preferred embodiment, invention has been described, but the invention is not limited in enforcement disclosed above
Example, and modification, the equivalent combinations that various essence of the invention are carried out should be covered.
Claims (10)
1. the fuel assembly stowage of a kind of pressurized-water reactor nuclear power plant, it is characterised in that include：
（1）Control system drives the cart and dolly of refueling machine to run to the predetermined full offset position of target simultaneously；
（2）The control system drives the main lifting of the refueling machine to drop to the first height；
（3）The control system drives the cart and trolley travelling to target location；
（4）The control system drives the main lifting to drop to reactor core bottom.
2. stowage as claimed in claim 1, it is characterised in that carry out step（1）Also include before：
Biasing is judged whether to according to the current location of the refueling machine, step is carried out according to judged result（1）Or step
（3）.
3. stowage as claimed in claim 2, it is characterised in that " judged whether according to the current location of the refueling machine
It is biased " specifically include：
Reactor core two-dimensional array figure is set up with the direction of motion dimension of the cart and the dolly；
The current location of the refueling machine is converted to into the position in the reactor core two-dimensional array figure；
Judge whether to bias using nine grids model and determine biased direction.
4. stowage as claimed in claim 3, it is characterised in that carry out " judging whether to partially using nine grids model
Put and determine biased direction " also include before：
Judge whether the target location is legal.
5. stowage as claimed in claim 1, it is characterised in that first height is at the top of reactor core at 8.7 meters.
6. the fuel assembly discharging method of a kind of pressurized-water reactor nuclear power plant, it is characterised in that include：
（1）Control system drives the cart and dolly of refueling machine to run to target location simultaneously；
（2）The control system drives the main lifting of the refueling machine to rise to the first height；
（3）The control system drives the cart and dolly to run to the predetermined full offset position of target simultaneously；
（4）The control system drives the main lifting to rise at the top of reactor core.
7. discharging method as claimed in claim 6, it is characterised in that carry out step（1）Also include before：
Biasing is judged whether to according to the current location of the refueling machine.
8. discharging method as claimed in claim 7, it is characterised in that " judged whether according to the current location of the refueling machine
It is biased " specifically include：
Reactor core two-dimensional array figure is set up with the direction of motion dimension of the cart and the dolly；
The current location of the refueling machine is converted to into the position in the reactor core two-dimensional array figure；
Judge whether to bias using nine grids model and determine biased direction.
9. discharging method as claimed in claim 8, it is characterised in that carry out " judging whether to partially using nine grids model
Put and determine biased direction " also include before：
Judge whether the target location is legal.
10. discharging method as claimed in claim 6, it is characterised in that first height is 8.7 meters at the top of reactor core
Place.
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| CN105005821B (en) * | 2015-05-27 | 2018-06-22 | 中国科学院合肥物质科学研究院 | A kind of optimum path search method of the ADS refuelling systems containing toggle |
| CN108352205A (en) * | 2015-10-28 | 2018-07-31 | 韩国水力原子力株式会社 | Nuclear fuel mobile management program and nuclear fuel management method of mobile applied to it |
| CN111354495A (en) * | 2018-12-24 | 2020-06-30 | 核工业计算机应用研究所 | Method for switching related assemblies for overhaul refueling of pressurized water reactor nuclear power station |
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| US4650634A (en) * | 1983-11-21 | 1987-03-17 | Westinghouse Electric Corp. | Quick release cushioned T.V. camera mount |
| CN1706004A (en) * | 2002-10-15 | 2005-12-07 | 里尔有限公司 | Method for loading nuclear fuel assemblies inside a nuclear plant reactor core and device therefor |
| CN1790552A (en) * | 2004-12-16 | 2006-06-21 | 中国核动力研究设计院 | Straight nuclear reactor fuel assembly refueling, loading and unloading technique |
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