瑞典专利SE534439C2 Method for moving fuel bundles in a reactor core during fuel loading operations

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专利摘要:
The method involves defining an even cycle fuel bundle shift map and an odd cycle fuel bundle shift map of fuel bundles to be shifted to another core location during an even fuel loading cycle and an odd fuel loading cycle, respectively. The fuel bundles to be shifted during the even fuel loading cycle are selected from the fuel bundles identified to be shifted in the even cycle fuel bundle shift map and fuel bundles to be shifted during the odd fuel bundle loading cycle are selected from the fuel bundles identified to be shifted in the odd cycle fuel bundle shift map. Independent claims are also included for the following: (1) a method for developing an equilibrium core loading strategy for a nuclear reactor (2) a group of core maps for a nuclear reactor, comprising an even cycle fresh fuel bundle map.
公开号:SE534439C2
申请号:SE0702778
申请日:2007-12-13
公开日:2011-08-23
发明作者:William Earl Russel
申请人:Global Nuclear Fuel Americas；
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专利说明:

534 439 The fuel bundles are arranged in a hearth in accordance with a hearth charging strategy. A usable core charging strategy typically ensures that the core and fuel bundles adhere to tennis margins (eg heating under critical power ratio (CPR) and along the length of individual bundles (kW / ﬁ)) and reactivity margins (eg Hot excess (HOTEX), shut down margin (SDM), and end of cycle (EOC). If ﬂ flattening of fuel bundles during refueling is used o ﬂ a to meet thermal and reactive margins for the core and individual bundles. The core charging strategy can also ensure that the fuel bundles do not exceed the permissible limits. The core charging strategy also determines the location and type of fresh fuel bundles to be charged during each refueling operation.
It has not been uncommon for a conventional core charging strategy to relocate most or all of the exposed fuel bundles to be reused. Extensive ﬂ removal of the bundles was done to achieve suitable thermal and reactive margin limits. Excess ﬂ surface increases the time needed to refuel in a hearth and increases the risk that the bundles will be placed in an incorrect hearth position.
A core strategy can have as a design goal an “equilibrium army” that adheres to the thermal and reactive margins and other core design criteria. An equilibrium hearth has minimal changes in the charge of its hearth fuel and the exposures of the bundles in the hearth between successive fuel periods. An equilibrium strategy promotes the use of the same charge plan of the fuel bundles, the ﬁ nitions for fresh fuel and rod pattern consumption from period to period. An equilibrium tactic for core charging minimizes core placements from which spent fuel is to be removed, new bundles are to be inserted and from which bundles are to be moved if taken and placed do not change significantly from a core charging period to another. Equilibrium typically requires ﬂ your fuel charge periods, e.g. 8 to 10 periods, to be achieved. The charge plan for the iron weight hearth represents a desired goal to be achieved in a hearth charging strategy that extends over ﬂ your fuel periods. The “Equilibrium Strategy” helps salespeople and customers to develop a long-term core charging strategy for financial and planning considerations. An iron weight hearth charging plan can be used to iron one hearth charging strategy with another.
To reduce the time required to charge the fuel bundles, a method and system for reducing the fuel bundles to be moved during each refill work is required. A fuel charging method and system should take into account a curing strategy for fresh fuel bundles, removal of burned fuel bundles and reuse of bundles 534 439 for two or three consecutive fuel periods. Selection of burnt bundles to be removed, identification of inconsistent bundles to be replaced and determination of their new core position, and selection of new bundles and identification of their core positions are determined by a core charging strategy.
There is a long-known need for a core charging strategy that simplifies the core charging process and reduces the time required to remove, relocate and charge fuel bundles in a core. There is also a long-known need for a core charging strategy that achieves equilibrium through a reduced number of charging periods and a balance that has a small change in core charge between successive charging periods.
Brief Description of the Invention An object of the present invention is to provide a method which simplifies the core charging process and reduces the time required to remove, relocate and charge the fuel bundles in a core.
Thus, a method is provided for during fuel loading work by means of at least one crane surface fuel bundles in a core of a core reactor, the core comprising a set of core positions according to a grid where each core position is constituted by a window in the grid and where each core position can be co-defined two which consists of two integers, wherein a core position which can be defined by means of two odd numbers or two iron numbers constitutes an even core position and a core position which can be defined by means of two coordinates which consist of an combination of an odd number and an even number constitute a odd core position, which grid comprises a central area, an outer area enclosing the central area and which outer area they are av niered by fuel bundles to be used for at least three fuel charge periods, and a perimeter enclosing the outer area, the method comprising: a) at a first fuel charge period: - remove the fuel bundles in even core positions in the central o the area of the core, - place the fresh fuel bundles in the even core positions in the central area, - remove the fuel bundles in the perimeter from the core, - move the fuel bundles in the even core positions in the outer area to the core positions in the perimeter, and place the fuel in the perimeter. even core positions in the outer area.
An embodiment may comprise b) at a second fuel charge period: - removing the fuel bundles in odd core positions in the central area from the core, - placing fresh fuel bundles in the odd core positions in the central area, - removing the fuel bundles in the perimeter of the core, odd core positions in the outer region to the core positions in the perimeter, and - place fresh fuel bundles in the odd core positions in the outer region.
An embodiment may, after the step of removing the fuel bundles in the perimeter from the core, comprise: - moving a fuel bundle from the center of the grid to the perimeter, and - placing a fresh fuel bundle in the middle of the grid.
An embodiment, after the step of removing the fuel bundles in the perimeter of the core, may comprise: - removing a fuel bundle from the center of the grid from the core, and - placing a fresh fuel bundle in the middle of the grid.
The coordinates that they. Deny the coordinates of the grid can begin their enumeration in the same corner of the grid.
An embodiment may include reading control inputs to de-ignite the core, which control inputs include a de ﬁ nition of the number of columns and rows in a quarter section of the core grid. 534 439 Brief Description of the Drawings Figure 1 is a schematic diagram of a core in a boiling water reactor.
Figures 2 and 3 are schematic diagrams of quartz sections of the hearth, with Figure 2 showing an “odd” charging pattern for fresh fuel bundles and Figures 3 showing a “uniform” charging pattern for fresh fuel bundles.
Figure 4 is a map of a quartz core section showing lines indicating an om ﬂ surface pattern for the fuel bundles, the map being generated using the om ﬂ surface algorithm described herein.
Figure 5 is a map of a quartz core section showing lines indicating an ﬂ distribution pattern of fuel bundles, the map being made using a conventional approach to fuel loading.
Figure 6 is a perspective view of a typical fuel bundle.
Figure 7 is a flow chart of a process for activities in a boiling water reactor period to period.
Figure 8 is a flow chart of a typical embodiment of the flow algorithms.
Figure 9 is a typical set of control inputs for the output algorithms.
Figures 10 and 11 are typical sets of hard charge strategy maps used as inputs to the ﬂ performance algorithm.
Figures 12 and 13 are typical period-end exposure maps for an odd and even core charge system, respectively.
Figures 14 and 15 show typical period start hardening maps indicating the exposure margin for each bundle, these urer gures showing that with the alg performance algorithms described herein, the exposure margin for almost all bundles is relatively close to a 10% design margin.
Figures 16 and 17 are typical period end hardening (EOC) maps showing the critical power ratio (CPR) for each bundle, with these estimates showing that with the distribution algorithm described herein, the critical power ratio margin is for almost all bundles. relatively close to a design exposure margin of%.
Figures 18 and 19 are typical period state (BOC, beginning of cycle) and period center maps (MOC, middle of cycle) for an entire core over shutdown margins for each fuel bundle in the core. Detailed Description of the Invention Figure 1 is a schematic two-dimensional top view of the core 10 of a boiling water reactor. The core comprises hundreds of control cells 12 (indicated by a dashed circle).
Each control cell comprises four fuel bundles 14 arranged around a control blade 17. For the sake of clarity, only one control blade is shown and only one control cell is designated in Figure 1. In a typical core, all or most of the fuel bundles are arranged in control cells. The core 10 is arranged in a two-dimensional arrangement in which each fuel bundle is assigned a specific group position.
Batch positions in the core are determined by a core charging plan which is carried out during core charging while the boiling water reactor is switched off and the core is available to remove expired fuel bundles, charge fresh fuel bundles and surface the bundles to be reused during the next period. A crane 16 over the core moves each bundle of fuel to its correct position in the core. The crane for ﬂ typically moves the fuel bundles in succession, e.g. one at a time. A base bed 18 near the reactor core is used to temporarily store fuel bundles. The crane for ﬂ is moved to the basin to discard burnt fuel bundles and grab fresh bundles.
Movements between the hearth and the basin are relatively long (compared to between hearth bundle positions) and require relatively long periods of crane movements. Similarly, passing the crane over large areas of the core requires longer periods of crane time than crane displacements between adjacent or adjacent fuel bundle positions in the core. Reducing the number of crane connections between the pool and the hearth and over large areas of the hearth will typically result in a reduction in the total time required to load fuel bundles into a hearth.
This describes a moving algorithm that decreases: the number of bundles to be relocated, the travel between a hearth and a pool, and the average distance traveled across the hearth during each lcran movement. The relocation algorithm generates, for example, a core map, e.g. Figures 2 and 3, which identify the hearth modes of burnt fuel bundles to be removed from the hearth and transferred to the pool and hearth modes to receive fresh fuel bundles.
A majority of fresh fuel bundles should be placed in hearth positions where burned-out fuel bundles should be removed. The tap 16 removes a burned out fuel bundle from the hearth, for ﬂ extends to the basin 18 in which the burnt out fuel bundle is placed in the basin at reference numeral, grips the fresh fuel bundle 22 intended for the recently emptied hearth position from the base bed, and for ﬂ moves back to the hearth to install the fresh fuel bundle in the same core position from which the burnt fuel bundle was removed a few minutes ago. l5 534 439 During a journey between the hearth and the basin, the crane has deposited a bundle of fuel in the basin and seized a fresh bundle of fuel for the hearth. The hearth map generated by the ﬂ surface algorithm reduces the journeys between the pool and the hearth by making a program for the crane to release a burned out bundle and pick up a fresh bundle during each journey.
The risk of placing the fresh bundle in the incorrect core position is minimized because only one fuel bundle position is empty in the core. The crane alternates between removing a spent fuel bundle and installing a new fuel bundle. The crane does not have to move ﬂ your burned out fuel bundles and thereby leave ﬂ your empty core positions. Having your empty hard positions for the fuel bundle increases the risk that a fuel bundle will be placed in the wrong core position.
The period required to charge a hearth depends in part on the number of fuel bundles to be redistributed from one hearth mode to another. The period needed to charge a hearth can be significantly reduced, e.g. by more than 50% of the replacement time and as much as 85%, if the number of fuel bundles to be replaced is reduced so that a large part, Lex. more than 50%, of the bundles to be reused not to be transferred from one hearth mode to another during fuel charging.
The relocation algorithm described here reduces the number of fuel bundles to be replaced. A change is the transfer of a fuel bundle used during a previous charging period to a new curing mode for a subsequent charging period. The number of ﬂ emissions is partly reduced by replacing the ﬂ most burned fuel bundles with fresh fuel bundles. The removal of burnt-out bundles and the installation of fresh bundles do not require relocation.
The displacement algorithm also reduces the number of arbet workings by limiting the ﬂ ests of ﬂ the ions to an outer annular area 24 in the core. The outer annular area 24 can be ﬁ nied by the fuel bundles to be used for at least three fuel charge periods. The outer annular core area does not include core positions at the perimeter of the core, where fuel bundles are located for a third fuel period.
During a refueling operation, the fuel bundles at the outer annular region 24 either remain in the same core position from the most recent fuel period or are ﬂ shifted to a core position at the perimeter 25 of the core. A fresh fuel bundle is placed in a hearth position where a bundle has been removed to be redirected to the perimeter. A fresh fuel bundle in the outer core area 24 remains in the same core position for two periods and is then redirected to a position in the perimeter for a third fuel period. 534 439 In the outer core region 24, the exposure to radioactivity of a fuel bundle during reactor operation is less than for the bundles in a central core region 26. The service life of a fuel bundle depends on its exposure level and operating time in the core. A fuel bundle with a high exposure level (as occurs in the central area 26) has a life of two fuel charge periods because they reach maximum acceptable exposure levels within exactly two fuel periods. The fuel bundles in the central hardening area 26 cannot be used for three fuel periods. The fuel bundles in the outer core area 24 receive less exposure to radioactivity. The fuel bundles in the outer core area have a longer service life of three fuel charge periods.
The central hardening area 26 within the outer annular area consists of fuel bundles having a life of only two fuel charge periods. Using the ﬂ spin algorithm ﬂ, the fuel bundles in the central core area are not redistributed, except for the bundle 28 at the center of the core. The fuel bundles in the central core area are either removed and replaced with a fresh bundle, or remain in their current core positions for a second fuel period. The central fuel bundle (s) 28 typically move during each charge period due to the high exposure level of a bundle (bundles) at the center of the core.
During each refueling, half of the fuel bundles in the central core area 26 (other than the central bundles 28) are replaced and the other half of the bundles are not moved.
Half of the fuel bundles that move during each core charging job change during each subsequent charging job. For example, at alternating core positions, the fuel bundles can be removed in the central core.
Figures 2 and 3 show quartz sections of a core 10 and show a typical charge pattern for the central core area 26 in which the heel of one of the fuel bundle positions is removed and replaced during each core charge operation. The core shown in Figures 2 and 3 is the same core. Figure 2 shows the bundles at the start of a period, e.g. an odd period, and Figure 3 shows the same hearth at the start of the next period, an even period. Figures 2 and 3 show the average fuel bundle exposure (GWD / T) for each bundle at the beginning of a period (BOC). Fresh bundles are designated “0.0” because they have no exposure. The bundles to be reused have an exposure value above zero, e.g. 23.2, 22.5 and 39.8, and well below the maximum exposure threshold at the start of the period, e.g. 40.0. These exposure values at the start of the period indicate the amount of radioactivity exposure for the bundle during the previous one or two periods. At the start of the period, the exposed bundles in the central area 26 of the core were 534,439 during the previous fuel period. Exposed bundles in the outer core area 24 may have been present in one or two previous fuel periods.
Design restrictions set exposure limits for each bundle at the start of the period.
The exposure limit varies for each bundle and the bundles towards the perimeter have a higher exposure limit at the start of the period, e.g. above 40.0, and the bundles in the middle of the core have a lower exposure limit at the start of the period, e.g. 24.0. The exposure limit at the start of the period can be determined so that a bundle has an exposure of no more than one exposure limit, e.g. 44.0, at the end of the period (EOC).
The pattern of fuel bundles to be removed from the central hardening area 26 may be similar to a chess pattern in which "white" positions in the pattern alternate with "black" positions in the pattern. During a core charge work, the fuel bundles at “white” positions from the central core area remain in place and the fuel bundles at “black” positions for ﬂ surface to the basin 18 and are replaced with fresh fuel bundles 22. During the next core charge work, the fuel bundles remain at “black” positions from the the central hardening area in place and the fuel bundles at “white” positions are moved to the basin 18 and replaced with fresh fuel bundles 22. The hardening charge of the central hardening area 26 changes back and forth from white to black during each subsequent hardening charging work.
Similarly, the fuel bundles in the outer hardening area 24 (not including the perimeter 25) may be arranged in a chess pattern in which the fuel bundles in the "white" positions are moved to the perimeter for a third period and replaced with fresh bundles, and the bundles in the The "black" modes are left in place for a second period. During the next period, the bundles at the white positions are left in place for a second period and the bundles in the black positions ﬂ are transferred to the parameter and replaced with fresh bundles.
Figures 2 and 3 are core exposure maps at the start of the period showing fresh fuel bundles (0,0) arranged in a chess pattern in the central core area 26. A comparison between ﬁ gur 2 and ﬁ gur 3 shows that the positions of the fresh bundles change in the chess pattern. Figure 2 can be used to map locations for fresh fuel bundles for a core charging job and Figure 3 can be used to map locations for fresh fuel bundles for the next core charging job. The next subsequent hardening work (third work) would have fresh bundles charged in the positions shown in Figure 2 at the central hardening area 26.
An alternative term for the white and black positions in the core is to refer to the core positions as odd and even positions. The core positions can be identified by reference to the coordinate numbers 1 to 30 along the left and upper margins of the core diagram shown in 534 439 Figure 1. For example, the central bundle position 28 is referred to as the 16-16 position. An even core position is denoted by a pair of coordinate digits that are both even or both odd. An odd core position is denoted by a pair of coordinate digits that include an odd and an even number.
During a first fuel charge period, the fuel bundles at odd core positions (ﬁ g. 2) in the central region 26 and the outer core region 24 (not including the central bundles 28 and the bundles at the perimeter) are not moved during core charging work. The bundles at even hardening positions (ﬁ g. 3) in the central area 26 are removed and replaced with a fresh bundle and in the outer hardening area 24 ﬂ the bundles are converted to the perimeter. During the next fuel charging work (which takes place after a fuel charging period), the bundles at even core positions in the central and outer areas 24, 26 are not moved during a core charge job. During the odd fuel charge period, the bundles are removed at odd core positions in the central area and replaced with a fresh bundle, and at the outer core area the bundles are moved to the perimeter.
The bundles at the perimeter are moved to the pool during each refueling period. The bundle at the center 28 of the hearth is either ﬂ relocated to the perimeter or moved to the pool.
With the ﬂ surface algorithm described here, the bundles to be moved are limited to a heel ﬂ of the bundles in the outer core area 26 and possibly the bundles at the center 28 of the core.
The even / odd (black versus white) core charging strategy to replace the fuel bundles has been used in the prior art. As far as the inventors are aware, previous uses of the smooth / odd core charging strategy were not compatible with a prescribed ﬂ discharge algorithm that generated core charge plans for a series of fuel charge periods and did not form part of an algorithm that generated a core charge strategy to equalize charge periods.
Using the ﬂ surface algorithm described here ﬂ, the fuel bundles in the outer core area 24 are typically shifted. The fuel bundles in the internal hardening area 26 ﬂ are typically not redistributed, with the exception of the central fuel bundle (s) 28 which are (ﬂ) redistributed during each fuel charging operation. Consequently, reassembly is performed primarily on a reduced set of core positions and in a limited area of the core.
Figure 4 is a typical map of a quarter section of the hearth with lines indicating the fuel bundles to be redistributed from one hearth position to another. Not all slin lines are displayed to reduce clutter. The bundles to be redistributed are underlined and twice burned bundles to be replaced by the redistributed bundles are circled in ﬁ g. The map shows that the fuel bundles to be redistributed are largely limited to the outer hardening area 24 and that relatively few bundles are redistributed compared to the conventional redundancy shown in 534 439 ll in Figure 5. The migration map shown in Figure 4 was generated using of the ﬂ performance algorithm described here.
Figure 5 shows, in contrast, a conventional ﬂ surface map with lines indicating the bundles to be moved from one core position to another. This conventional ﬂ map shows a significantly larger number of bundles being moved and bundles traveling a greater distance across the core than the artan map shown in Figure 4. While conventional techniques have not always changed as many fuel bundles as shown in Figure 5 (especially with with respect to the conventional approach odd versus even with respect to charging fresh bundles), ﬁ gur 5 is representative of the extensive relocation of fuel bundles that is conventionally performed during fuel charging periods.
An iron transfer between 4 gur 4 and 5 shows a reduction in the number of bundle shifts in a refueling strategy generated using the ﬂ gassing algorithm described here compared to the number of ﬂ gears shown in ﬁ gur 5. The number of ﬂ gears was significantly reduced, e.g. by approximately 86%, using the ﬂ surface algorithm described here to generate the ﬂ surface map shown in Figure 4 compared to the surface map shown in Figure 5. In addition, if the surfaces shown in Figure 4 require the bundles to travel relatively short distances across the core, compared with the distances for the ﬂ expansions shown in ﬁ figure 5. By reducing the number of relocations and the om expiration distances, the downtime due to fuel loading can be reduced by ﬂ your days, e.g. a saving of three to five days. It is estimated that some boiling water reactors produce $ 1 million in profit per day.
Using this estimate, a three-day reduction in downtime adds an additional $ 3 million in profit for each refueling period of the boiling water reactor.
Figure 6 shows a typical fuel bundle 14. A hearth typically comprises 200 to 1200 fuel bundles. Each bundle includes an outer channel 30 surrounding a plurality of fuel rods 32 extending generally parallel to each other in a generally rectilinear array of fuel rods.
The rods 32 are separated laterally from each other by spacer elements 34 at different vertical heights along the length of the fuel rods and the channel. The bundle includes a handle 36 hooked by a crane to lift the bundle out of a hearth or basin, move the bundle into position over the hearth, and lower the bundle to a new position in the hearth or basin.
Each fuel bundle 14 may have special driving characteristics, e.g. thermal and reactive margins. The properties of the bundle depend on the types and arrangements of fuel rods loaded in the bundle. Due to the fact that the bundles have different properties, e.g. fuel rod assembly, one bundle may not necessarily be easily replaced by another bundle. 10 534 439 12 Fuel bundles that have the same properties are referred to as belonging to the same type. A hearth typically has typer your types of fuel bundles, Lex. seven or ﬂ are. A determination is made as to the type of fuel bundle to be used at each fuel bundle position. This determination can be made outside the ﬂ performance algorithm. An input matrix can be provided as an input to the ﬂ distribution algorithm. A typical input matrix is shown at reference numeral 82 in ﬁgur. The longitudinal matrix indicates a type of fuel bundle, e.g. 1 to 7, for each bundle position in the core. The input matrix is a constraint of the output algorithms. The algorithm generates a core charging strategy that plans to charge the bundles that have the type of fuel specified in the input matrix for each core mode.
Figure 7 is a flow chart 50 of a process for downtime activities for a boiling water reactor period to period. A boiling water reactor produces steam for energy generation during a working period of typically one or two years, e.g. 12 to 24 months, in step 52. A planned shutdown of the boiling water reactor occurs at the end of each fuel period (EOC). After the reactor is shut down, the reactor vessel is disassembled, step 54, to open the reactor core for maintenance, repair and fuel charging. Disassembly of the reactor is typically a three to four day process. Once the reactor is available, maintenance of control rods and other components in the core is performed. The fuel bundle can be removed, step 56, to provide access to the control rods and other components to be inspected, repaired or replaced, step 58.
Typically, three to five days are required to remove the fuel bundles and to inspect, repair and replace core components in steps 56 and 58.
The core is ready for the fuel charging process after maintenance activities have been completed in the core. In step 60, spent fuel bundles (eg bundles at or near an exposure limit at the end of the period, eg 44.0) are removed from the core, fresh bundles are loaded into the core, and bundles to be reused are left in their current core positions or ﬂ replaced to a new mode. A crane (taps) is typically used to move the fuel bundles between the hearth and a basin and to move the bundles to new positions in the hearth. While conventional fuel charging work to surface the fuel bundles typically requires seven to fourteen days, the movement of the fuel bundles can be reduced to three days (and even fewer days) using the displacement algorithm described herein. The moving algorithm can be used to reduce the number of bundles to be redistributed and to reduce the distance as if the floating bundles are to be swept across the core. It is assumed that the removal work can be reduced to half a day's work, compared with a three to seven day work in a conventional charging work which does not use the moving algorithm described here. 534 439 13 After the fuel bundles have been loaded into the core and all maintenance and inspection work has been completed by the core, the reactor vessel is assembled in step 62. The reactor performs a start-up procedure, in step 64, and begins the next period. At the start of the next period, the core is at the beginning of the period (BOC). The reactor produces energy for another one to two years, in step 52, so that the fuel period is repeated. The fuel period is repeated during the life of the boiling water reactor.
The displacement algorithm described here simulates the periods of the boiling water reactor and looks forward to an equilibrium period in which the fuel maps between similar periods in time and charging strategy have minimal differences between them. The ironweight fuel charge map is a target used for the fuel charge strategy.
Figure 8 is a flow chart of a typical embodiment of the move algorithm 70 described herein. The relocation algorithms 70 herein may be part of a process, process, and design strategy to provide core charging programs that minimize the transfer of fuel bundles between successive fuel charge periods of a boiling water reactor. The algorithm 70 may be encoded in an executable computer program that provides user input control over key function parameters. The computer program can be executed in a computer used to develop core structures for the boiling water reactor.
The relocation algorithms generate alternative core fuel charge maps to be used for consecutive core charge periods. The core maps have central areas and outer core areas in which the positions for fresh fuel bundles and for the bundles to be maintained for a second period are arranged in a pattern. These charging patterns for the central hardening area can be reversed from one charging period to another. A comparison between 2 gur 2 and 3 shows examples of core charge maps for successive core charge periods.
The hardening charge maps in Figures 2 and 3 each have a central area 26, and the hardening charge is limited to removing burnt bundles and installing fresh bundles at the same locations from which the burned out bundles were removed. The charging pattern for fresh bundles is a mirror image of the charging pattern in Figure 3.
The fact that they ﬁ nier a central core area in which the bundles are not relocated excludes a large part of the core modes from being relocated, Lex. about 86% of all core modes. Segmentation of the hard in an outer annular area 24 in which the bundles ﬂ are relocated and a central hardening area 26 in which the bundles are not moved (except at the core center 28) reduces the number of ﬂ expansions to be performed during each core charging work and reduces the time required for . 534 439 14 Figure 9 is a diagram of an example of control inputs 74 for the ﬂ performance algorithm 70. The control inputs are loaded into the algorithm to de ﬁ the core of the algorithm, in step 72. The control inputs may prescribe the number: columns and rows in a quarter section of the core, fresh bundles to be charged in the quartz section of the core during each charging period, the total number of bundles in the quartz section of the core, and thermal hydraulic type. The thermal hydraulic type is an inlet that indicates the type of fuel bundle in the core and can be specified by the user. The inputs 74 may also indicate the number of fuel charge periods, e.g. two, which form a loop. Figures 2 and 3 show a loop of two periods in which every other charge map for fresh fuel is substantially the same. A loop is the result of fuel charge periods used to vary the pattern of charging fresh fuel bundles.
The user can also specify whether the core charge map should be an "odd" or "even" pattern for charging fresh fuel bundles. The choice of odd and even assumes a loop of two periods. If the loop includes three or perio er periods, the choice of charge can be any of 1, 2, 3, etc. (rather than odd and even). The choice of the charging pattern, e.g. odd or even can be done manually in step 76. The user who sets up the ﬂ algorithm may only need to select odd or even, but can also review and modify andra your other input parameters for the ﬂ algorithm. The selection of the odd or even charging system can be performed automatically based on data indicating whether the previous charging period was odd or even and selecting an opposite charging pattern for the next period.
The inputs in 9 gur 9 may also include input soms as they ﬁn an earlier iteration of the fuel bundles in the core. These inputs can be generated by a conventional core simulation program that reliably predicts the state of the core and its fuel bundles over a fuel period. The simulation program generates data on the condition of the fuel bundles in the core during a fuel period. This data is used by the flow algorithm 70 to generate fuel charge maps for the next refueling period. The introductory letters may include the initials of fresh bundles, period start letters, period start qualifiers, period end letters and period end qualifiers, provide constraints to be used by the performance algorithm in generating performance maps.
For example, the initials of fresh bundles are a common identifier, e.g.
'C05', used for all bundles added to a special refueling operation of the fuel bundles; file period start letters, e.g. "Rods.ced", refers to data, e.g. exposure values, regarding the fuel bundles at the beginning of the fuel period (BOC) in the previous fuel period, and period the period end bars are data about the fuel bundles, e.g. exposure values for the bundle, at the end of a period (EOC); and the period start and period end qualifiers are data identifiers, Lex. bundle handling number, for each of the fuel bundles in the core. The core simulator can generate data for the period start and period end bars.
In step 78, fuel bundle strategy maps are loaded across the core as inputs to the migration algorithm. These maps are templates used by the ﬂ replacement algorithms to determine which fuel positions should have bundles not to be replaced during the next period, positions to receive fresh bundles, positions from which bundles are to be emptied, and positions from which bundles are to be moved.
Figures 10 and 11 are typical strategy maps. The strategy maps may include a fuel location map 80 that identifies all fuel bundle positions in the core (where “l” or indicates the positions of the fuel bundles, and “0” or indicates positions without any fuel bundles and outside the core); a fuel type map 82 identifying the type of fuel bundle to be located at each position of the core (where numbers 1 to 7 represent which of seven possible types of fuels is to be placed in each core fuel bundle location); a fuel emptying position map 84 identifying the core positions having the fuel bundles to be removed due to the bundles having undergone three periods (where “l” or indicates the modes having the fuel bundles completing a third fuel period); a position chart 86 of fresh bundles for an odd period (where “l” or indicates the positions where fresh bundles are to be installed, and “0” or indicates the fuel bundles that are to remain in their current positions during a second fuel period); a position map 88 of fresh fuel bundles over an even period (where "l" or indicates the positions where fresh bundles are to be installed, and "0" or indicates the fuel bundles that are to remain in their current positions during a second fuel period); a map 90 of twice burned fuel (also referred to as the odd periodic fuel bundle ﬂ map) for the odd periods indicating the core positions of fuel bundles that have undergone two fuel periods and are to be ﬂ converted to perimeter (see map 84) for a third period ( where “l” or indicates the positions of twice burned fuel bundles), and a map 92 of twice burned fuel (also referred to as the periodic fuel bundle ﬂ performance map) for the even periods indicating the core positions of the fuel bundles that have undergone two fuel periods and to be moved to the perimeter (see map 86) for a third period (where "1" or indicates the positions of twice burned fuel bundles). These maps 80 to 92 identify the fuel bundle modes in the core where: fresh bundles are to be installed, bundles to be reused during a second period are to remain in their current positions, and from which bundles are to be moved for reuse during a third period. Although subject to a separate 534 439 16 fuel bundle template, the fuel bundles to be emptied, e.g. for ﬂ transferred to a basin, after two fuel periods subject to location maps of fresh fuel bundles that are also not included in the maps of twice burned fuel.
The fuel bundle charging strategy maps 80 to 92 can be modified by the user or using optimization tools in step 94. The optimization tool may be a computer software program that interferes with one or more of the maps 80 to 92. The disturbed maps are input to the surface flow algorithms to determine whether an improved charge can be . An example of an optimization tool is described in commonly assigned and also decided U.S. patent application serial number 111/610, l97, which is incorporated in its entirety by reference. For example, the optimization tool may interfere with the map 82 of fuel types at each flash mode. The disturbed map 82 is input to the relocation algorithms to study and improve the selection of fresh bundles and maintain requirements for thermal margins, requirements for reactivity margins, and improvements in fuel period efficiency.
In step 96, the ﬂ emission algorithm reads information regarding the previous fuel charge period. The previous fuel charge period may be the exhaust from a core simulator that modeled the operation of the core and its bundles based on the period before the one running through the move program. Data for the previous periods are provided by the elements specified in the introductory lines shown in Figure 7 and include data for period start and period end wooden sticks and period start and period end qualifiers.
A period end exposure map for the previous period is useful in determining the amount of exposure for each fuel bundle at the end of the period. By comparing the period-end and period-start exposure maps (eg, comparing data for period-end and period-start tree sticks), the amount of exposure that each core creep mode is predicted to experience during the next fuel period can be used to estimate the amount of exposure expected at the same position during the next period. The exposure prediction may be that each core bundle mode will experience the same amount of exposure during the next period.
Figures 12 and 13 are examples of period end exposure maps (eg data for cedar sticks). Examples of period start exposure maps (eg cedar rod data) are shown in Figures 2 and 3. The exposure of each bundle during a single fuel period can be obtained by comparing the exposure of the fuel bundles at the start of the period (see Figures 2 and 3) with the period end exposure (EOC). ) for the same fuel bundle, as shown in Figures 12 and 13. Figures 12 and 13 show the average exposure (GWD / T) for each fuel bundle in the core at the end of the period. Figure 12 shows an “odd” fuel map and corresponds to Figure 2 in that Figure 12 534 439 17 shows fuel bundle exposures at the end of the period for the same fuel bundles as shown in Figure 2 where Figure 2 shows the exposure for the bundles at the start of the period.
An outer ring-shaped area 89 of positions for fresh bundles (map 88) in an even fuel charge period is the same as positions for twice burned bundles from this even period (map 92). During an even fuel period, the twice burned fuel bundles are removed (map 92), e.g. bundles that have already experienced two fuel periods, from the positions shown in map 92 and ﬂ are transferred to the perimeter of the core, e.g. to the emptying modes indicated in map 84.
Fresh bundles are placed in the left positions for the bundles to be redistributed, where the left positions are identified by map 92. Fresh bundles placed at the outer ring of the map 88 over even fresh bundles are left in this position for two fuel periods and ﬂ are then transferred to the emptying mode (map 84) for a third period. Similarly, the odd fuel charge period (map 87) has an outer ring that overlaps the map 90 over twice burned fuel for the odd period. Consequently, the bundles to be replaced can be limited to the bundles to be transferred to the emptying positions (map 84) at the perimeter of the core, which are the bundles to be subjected to a third period.
In step 98 of the relocation process 70, an error check of the inputs is performed. For example, the map entries in Figure 8 can be analyzed to confirm that they take into account all bundles. The total number of bundle positions in the emptying map (obtained by summing the "l" oma in map 84) should be equal to the number of twice burned fuel bundles to be redistributed for each of the odd and even maps 90 and 92. Another error check is to confirm that the total number of core bundle modes (each mode is denoted by the number 1 in map 80) is equal to the combined sum of: (i) bundle tuning modes (each mode is denoted by number 1 in map 84), (ii) fresh bundle modes in the periodic map of fresh bundles 88 (each position is denoted by the number 1 in map 88), and (iii) locations of fresh bundles in the odd periodic map of fresh bundles 86 (each position is denoted by the number 1 in map 86).
In step 100, the expression algorithm determines the position-dependent exposure value for each bundle position. This value is the exposure that each bundle experiences over a period of time.
The exposure value can be obtained by subtracting the period end exposure from the period start exposure ßr each bundle, e.g. subtract the exposure value in ﬁgur 12 from ﬁgur 2 for each bundle. Similarly, ﬁ Figure 3 is a period start exposure diagram for a smooth fuel map and corresponds to the period end map shown in Figure 13. The exposure experienced by the core with the fuel bundle pattern shown in Figures 3 and 13 is the difference between the exposure values according to Figures 13 and 3. for each fuel bundle. The exposure experienced by 534 439 18 each bundle during the period is used by the ﬂ distribution algorithm to determine which fuel bundle can be moved to another core position.
In step 102, the ﬂ rendering algorithm rates the exposure levels for each of the bundles to be ﬂ redesigned. These bundles are at positions identified by the fuel maps 90, 92 over twice burned fuel. If the period currently being evaluated by the algorithm is an “even” period, the previous period was an odd period and the odd fuel map 90 of twice burned fuel identifies bundle modes from the most recent period that have bundles to be om to be replaced. . The period-end exposure map from the previous period, e.g. ﬁ gur 13 (odd period end), provides input data, e.g. för l for the period-end procedure, to determine the exposure levels for each of the bundles to be redistributed. The relocation algorithm grades, e.g. lowest to highest, the period-end exposure values for each of the bundles to be redistributed. In addition, the gradation can take into account the type of bundle in each position to be replaced. For example, the bundles can be graded in two dimensions, where one dimension is the type of fuel in the bundle and the other dimension is the exposure level of the bundle. The gradation helps the surface algorithm to identify the bundles to be transferred to new core positions at the perimeter as identified in the core drain map 84.
In step 104, the move algorithm generates ﬂ execution instructions, e.g. an ﬂ performance map that identifies a new core position for each bundle to be om replaced. When determining a new core position for each bundle to be redistributed, the algorithm uses the period-end exposure level rating (which identifies the exposures for the redistributed bundles from the previous period and possibly the type of fuel) to identify the appropriate bundles to be redistributed. for ﬂ is transferred to a new core mode, e.g. hardening positions near the perimeter as indicated by the emptying map 84. The expected exposure at each of the positions identified in the emptying map 84 can be obtained from the difference between the exposure levels at the end of the period and the start of the period for the bundles at these emptying positions during the previous period.
Knowing the exposure levels expected during the next period at each of the emptying modes and the gradation of exposure levels for the bundles to be moved (maps 90 and 92), the distribution algorithm can identify the bundles with the lowest exposure for switching to the highest emptying modes. expected exposure during the next period.
In this way, the relocation algorithm generates a redirection map where each bundle is to be redeployed. If the flow chart can identify in which emptying hardening positions (see map 84) each of the twice used bundles (see map 90 for an odd refueling period and map 92 for an even period) should be placed. 534 439 19 Step 106 is used if the ﬂ instruction instructions were used to generate a core map that identifies the fuel bundle at each bundle position in the core. Data for constructing a core map are available from databases. Data includes the relocation instructions (which identify the bundles in the emptying modes - see map 84); the location map of fresh bundles (either map 90 if the period is odd or map 92 if the period is even), and the period end exposure map from the previous period, shown in Figures 12 and 13. The period end exposure map provides exposure information for the fuel bundles that will remain in the same hearth during the next fuel period. and for the bundles of fuel that are moved. All other fuel bundles used during the next period are fresh.
Depending on whether the next fuel period is an even or odd fuel period, the generated exposure map is either an even period period exposure chart or an odd period as shown in Figure 2 or 3. Using the next period exposure map, a computer simulates the next fuel period for the hearth. Reactor simulators are conventional and beyond the scope of the present invention. U.S. Patent 6,748,348, entitled "Design Method for Nuclear Reactor Fuel Management" and discloses William E. Russell, II, who further describes a typical reactor simulator. The reactor simulator generates data that predicts the end of the simulated fuel period. The relocation algorithms can be used independently with manual calculations and with close incorporation of three-dimensional (3D) optimization tools to achieve maintenance of all thermal and reactive performance criteria for the reactor core. Different core design strategies including simulators for “Control Cell Core” and “Conventional Design” can utilize the ﬂ surface mapping method described here.
The generated data includes ﬁ l for period end cedar wood (see ñg. 9) in the user inputs 74 to the ﬂ rendering algorithm. The simulator can also output data regarding the period start of the simulated period, including the period start cedar tree. In step 108, the data on the period start and period end fuel bundles generated by the simulator are saved as data and made available for step 96 in the next iteration of the ﬂ flow algorithm when it generates ﬂ flow instructions for the next fuel charge period.
After the simulator generates data about the expected next period, e.g. period start-up and period-end exposure maps, the move algorithm switches the odd / even setting in the user input field 74 (ﬁ g. 9). The relocation algorithm is restarted for another fuel charge period, which is the period immediately after the most recent period that the relocation algorithm and the simulator have simulated. Before restarting, the algorithm changes from 534 439 odd to even or even to odd in step ll0. The relocation algorithm and the simulator run through successive fuel periods.
A loop of fuel periods with odd and even fuel patterns is shown by the sequence of ﬁgur 2 to ﬁgur 12 to ﬁgur 3 to ﬁgur 13 and back to ﬁgur 2. Figure 2 represents an odd pattern of fresh fuel hearths in the central area 26. The Exposure levels shown in Figure 2 are at the start of the period. Figure 12 represents the exposure levels of the fuel bundles at the end of the period of the same odd pattern as shown in Figure 2. In Figure 12, e.g. the fuel bundles in the central core area 26 either bundles (see bundle at core mode column 14, row 10, which has an exposure of 43.9) which have undergone two periods and are close to their exposure limit of 44.0 or the bundles which have only served one period and are ready to earn a second period in the same position (see bundle at column 14, row 1 l which has an exposure of 23.4).
During an odd fuel period, the exposure levels for the fuel bundles at the start of the period are as shown in Figure 2 and are as shown in Figure 12 at the end of the period. Similarly, Figure 3 represents an even pattern of fresh fuel core locations in the central area 26.
The exposure level shown in Figure 3 is at the start of the period. Figure 13 represents the exposure levels for the fuel bundles at the end of the period of the same even pattern shown in Figure 3. During an even fuel period, the exposure levels for the fuel bundles at the start of the period are as shown in Figure 3 and are as shown in Figure 13 at the end of the period. The loop of fuel periods through the smooth and odd patterns of fuel charge is shown by the sequence of ﬁ gur 2 and 12 which constitute one period, and the sequence of ﬁ gur 3 and 13 which constitute the second period.
The loop is the two periods together. The loop is repeated during the life of the boiling water reactor.
Figures 12 and 13 show period end bundle maps that reflect the results of the ﬂ shift algorithm. Almost all fuel bundles to be emptied have exposures of between 42 to 47.3, which is a small area. At the perimeter of the core where the bundles undergo three periods, exposures are in a range of 5 GWD / T. Due to the fact that the emptying bundles, especially at the perimeter, are all very close in exposure, the concern is minimized that one of the fuel bundles will experience an excessive exposure compared to the other bundles. Consequently, the total emptying exposure limit can be increased.
The relocation algorithm continues to go through even and odd fuel periods until an equilibrium solution is reached. The algorithm 70 stores the generated relocation instructions for interoperating periods. These successive core charge maps together become part of the core charge strategy over the life of the reactor. The listening method described herein can also be used to provide radial enrichment utilization that provides more enriched rings against the perimeter of the core, reduced enrichment at control cell positions, and reduced enrichment along axial lines have also been developed in accordance with this new method.
Curing constructions of boiling water reactors that have utilized the ﬂ flow algorithm described here have been found to be very similar to curing operating properties, e.g. exposure levels, for consecutive periods, even if the new modes between two periods are different. The hardening cartons provided by the ﬂ surface algorithm described herein have been used to minimize emptying exposure and provide sufficient thermal margins, reactivity margins and excellent fuel period efficiency. The core charging plans developed using the algorithm described here have yielded charging strategies with 86% fewer ﬂ performances than traditional core charging strategies. The reduction in the displacement of the fuel bundles results in reduced reactor downtime, e.g. reduction of downtime by ﬂ your days. The reduction in downtime days is translated directly into additional days with energy generation and profit from energy generation. It is estimated that a boiling water reactor can generate one million USD of energy per day. Through this measure, each reduction of one day during downtime results in a profit of one million dollars for each charging period.
Although reducing relocation time is important, it is important that the design provide the required thermal margins, reactivity margins, and desired energy.
The simulator step 106 may include a check to confirm that the core plane e.g. the core map at the start of the period over the fuel bundles, meets all design constraints such as safety margins. To a lesser extent, but also important for equilibrium studies, the constructions should also show similar comparisons between successive periods. For example. it is advantageous for the purpose of equilibrium for two consecutive odd fuel periods to have similar exposures and performance and similarly that two consecutive even fuel periods have similar exposures and performance. In fact, equilibrium can be determined to have been achieved when successive iterations in even periods of the moving algorithm and core simulations give similar results and / or successive iterations in odd periods of the moving algorithm and the core simulation give similar results. Because the ﬂ exposure method analyzes bundle exposure, e.g. bundle consumption, during the previous period and determines the position-dependent potential for exposure accumulation, a bundle is created that best utilizes this position through the relocation method. Charging strategies that meet design criteria are achieved through the ﬂ performance algorithm. 534 439 22 Figures 14 and 15 show odd and even period start maps of the hardening bundles where the values, Lex. 0.886 (at core position 13-16), corresponds to the margin between the exposure limit at period start and the actual period start exposure for the bundle. The hardening position of the fuel bundles shown in Figures 14 and 15 was determined by the surface flow algorithm. The moving algorithm is useful in producing hearths that have bundles that all work close to structural targets.
A margin value of 0.886 indicates that the bundle has an exposure of 88.6% of the exposure limit, which corresponds to a margin of 11.4%. A design goal is to have a 10% margin. The exposure limit is set for each bundle position and depends on whether the bundle at the position should serve one or two additional periods and the amount of expected exposure at this position during the next period. The margins of all the bundles shown in the hearth maps in Figures 14 and 15 are quite close and generally between a margin of 25% to 11%, except at the perimeter of the hearth. Establishing a core map so that the bundles in the core are relatively close to a design goal is advantageous and indicates good utilization of the fuel bundles.
Figures 16 and 17 show critical power ratio limits (CPR) at the end of the period for each bundle in an odd (ﬁ g. 16) and even (ﬁ g. 17) fuel period. These figures show that the bundles are close to the constructive critical targets for a power ratio of 0.85 (a 15% target).
Figures 18 and 19 are typical diagrams at period start (BOC) and period center (MOC), respectively, for an entire core over the shutdown margins (SDM) for each cell in the core. These diagrams show the shutdown margin of a fuel charge map generated using the ﬂ emission algorithm described here. The shut-off margins are relatively uniform in that most shut-off margins are in the range of 2.2 to 1.4 at the start of the period and 2.7 to 1.3 at the middle of the period, except at the perimeter and the center of the core. A relatively narrow range of shut-off margins, as shown in Figures 18 and 19, indicates efficient fuel charge.
New views on the process and system described herein may include: an automated solution for regenerating ﬂ clearance instructions for each fuel charge period; a ﬂ performance algorithm that can be used in conjunction with a core simulator to develop an iron weight core strategy; used inputs and data from previous fuel charge periods are used to determine ﬂ emission modes; exposure accumulation potential; The ﬂ algorithms can be used with manual optimization tools and / or software-based optimization tools to develop improved ﬂ performance instructions; ﬂ the delivery algorithm can be used with a variety of fresh fuel utilization plans; the displacement algorithm can be used to place bundles with higher enrichments against the perimeter where the bundles experience longer exposures, and ﬂ the displacement algorithm contains low enriched bundles at positions for control cell work supporting low enrichment along axes for consideration of adjacent sides, and the displacement algorithm automatically selects twice burned fuel bundles to be redirected to perimeter positions where the redundancy is determined based on exposure and travel distance.
Technical effects of the method and system described herein include: core charge design with major principles; better utilization of kW / ft at the start of the period; better utilization of critical power ratios at the end of the period, and better emptying exposure at the end of the period; solutions with good-looking iron weight and no replacements. Commercial benefits of the process and system described herein may include: tailored downtime of three days or less; increase in profit through longer energy production periods resulting from the shorter downtime periods; lower labor costs due to shorter downtime periods; fewer refuelings result in a reduced risk of fuel charge failures and rapid core construction solutions without refurbishments.
Although the invention has been described in connection with what is currently considered to be the most practical and preferred embodiment, it should be understood that the invention should not be limited to the described form of desiccation, but on the contrary is intended to cover various modifications and corresponding arrangements included within the scope. and the scope of the appended claims.

权利要求:
Claims (1)
[1]
A method for, during fuel loading work, by means of at least one crane (16) tta surface the fuel bundle in a core (10) in a core reactor, the core (10) comprising a set of core layers according to a grid where each core position consists of a window in the grid and where each core position can be medel niered by two coordinates consisting of two integers, a core position which can de be niered by two odd numbers or two even numbers constitutes an even core position and a core position which can be ﬁ niered by two coordinates consisting of a combination of an odd number and an even number constitutes an odd core position, which squarely comprises a central region (26), an outer region (24) enclosing the central region (26) and which outer region (24) is defined by the fuel bundles to be used for at least three fuel charge periods. , and a perimeter (25) enclosing the outer region (24), the method comprising: a) at a first fuel charge period: - removing the fuel bundles in even core positions in the central area (26) from the core (10), - place fresh fuel bundles in the even core positions in the central area (26), - remove the fuel bundles in the perimeter (25) from the core (10), - dry the fuel bundles in the even ones the core positions in the outer region (24) to the core positions in the perimeter (25), and - place fresh fuel bundles in the even core positions in the outer region (24); b) during a second fuel charge period: - remove the fuel bundles in odd core positions in the central area (26) from the core (10), - place fresh fuel bundles in the odd core positions in the central area (26), - remove the fuel bundles in the perimeter (25) from the core (10), - move the fuel bundles in the odd core positions in the outer region (26) to the core positions in the perimeter (25), and - place fresh fuel bundles in the odd core positions in the outer region (26) ). . A method according to claim 1, after the step of removing the fuel bundles in the perimeter (25) from the hearth (10), comprising: - moving a fuel bundle from the center (28) of the grid to the perimeter (25), and - placing a fresh fuel bundle in the middle (28) of the grid. The method of claim 1, after the step of removing the fuel bundles in the perimeter (25) from the core (10), comprising: - removing a fuel bundle from the center (28) of the grid from the core (10), and - placing a fresh fuel bundle in the middle (10). 28) of the grid. . Method according to one of the preceding claims, wherein the coordinate digits defining the coordinates of the grid begin their enumeration in the same corner of the grid. . A method according to any one of the preceding claims, comprising: - reading control inputs (72) allowing the core core, which control inputs comprise a definition of the number of columns and rows in a quartz section of the space of the core (10).

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法律状态:

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