CN107945889B - Method for realizing nuclear reactor load tracking - Google Patents
Method for realizing nuclear reactor load tracking Download PDFInfo
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- CN107945889B CN107945889B CN201711214357.XA CN201711214357A CN107945889B CN 107945889 B CN107945889 B CN 107945889B CN 201711214357 A CN201711214357 A CN 201711214357A CN 107945889 B CN107945889 B CN 107945889B
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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
- G21C7/08—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 by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
- G21C7/117—Clusters of control rods; Spider construction
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- G—PHYSICS
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- 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
- G21C7/08—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 by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
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Abstract
The invention discloses a method for realizing load tracking of a nuclear reactor, which adopts two sets of relatively independent control rod sets for controlling reactivity and axial power excursion power of the nuclear reactor; the two sets of control rod groups are respectively a T rod group and a K rod group, wherein the K rod group consists of a plurality of beams of black rods, and the T rod group comprises a plurality of beams of gray rods and black rods; during base load operation of the nuclear reactor, only the K rod sets are inserted into the core, and the insertion depth of the K rod sets is greater than or equal to the bite amount plus 24 steps; during load following operation of the nuclear reactor, the T-bar set and the K-bar set are each inserted into the core. The method only needs one group of control rods to be inserted into the reactor core during the base load operation, and the method avoids the defects of uneven fuel consumption, increased control rod injection, more control rod absorber fuel consumption, increased control rod drive mechanism load and the like caused by excessive control rod insertion into the reactor core during the base load operation.
Description
Technical Field
The invention relates to the technical field of design and operation of pressurized water reactor nuclear power plants, in particular to a method for realizing load tracking of a nuclear reactor.
Background
If a unit of a pressurized water reactor nuclear power plant needs to track the load along with the power grid requirement, the reactor power needs to be adjusted by adjusting the reactivity, and the implementation means mainly comprise the following two steps: 1) adjusting the boric acid concentration in the primary coolant; 2) the insertion depth of the control rods in the core is adjusted. The first adjustment requires the dilution or boronation of the primary coolant by injection of water or high boron concentration solution into the circuit by chemical and volumetric control systems. Since boron enrichment and dilution take some time, it is also slow to regulate reactor power. On the other hand, if the power plant load needs frequent elevation and tracking the elevation in a manner of adjusting the boron concentration alone, the main coolant needs frequent dilution and boronization, and a large amount of boron waste liquid needs to be treated. The second regulating means regulates the reactor power by inserting and extracting the control rods in the reactor core, and the speed of the regulating means is higher. However, the movement of the control rods in the core during operation causes the power distribution of the core to be distorted and even possibly cause unacceptable power distribution, and causes the problems of axial imbalance of the nuclear fuel consumption of the core, so that the use of the control rods to regulate the power of the reactor has certain restrictions and difficulties.
The early designed pressurized water reactor nuclear power plant only has one set of control rods (except for shutdown rod groups), all the rod groups are inserted and drawn in sequence according to a certain overlapping step number, and the single bundle of control rods has stronger neutron absorption capacity and is called as black body control rods. In this mode (mode a), if the reactivity variations due to the power variations are all compensated by the control rods, the axial power distribution imbalance is likely to last longer, the operating conditions of some parts of the fuel assemblies are degraded, hot spots may occur, and the long-term imbalance of the core axial power distribution may cause the axial burn-up distribution of the core kernel fuel to be uneven. Therefore, the control rods are mainly used for adjusting the axial power deviation of the core and simultaneously compensating the average temperature of the core coolant, and when the two contradict each other, the reactivity change difference is borne by the boron adjusting system. The reactor load following capability is significantly limited due to the time required for primary coolant boron concentration adjustment.
Later, france designed a mode (G-mode) that employed a partial gray control rod. The power compensation rod groups of the ash-containing control rods are mutually overlapped, and the axial power distribution distortion of the reactor core caused by the movement of the power compensation rod groups is not serious because the ash-containing control rods have weaker neutron absorption capacity. The depth of insertion of the power compensation rod set into the core is power dependent, and the core is fully extracted during base load operation and inserted for power regulation during load following. Another set of control rods is dedicated to adjusting the axial power offset and core coolant mean temperature, and is inserted in the upper core during both base load and load following. In this mode, the reactor power can be quickly adjusted without changing the boron concentration of the primary coolant to adjust for rapid reactivity changes due to power changes caused by temperature feedback effects and the like. However, the slow reactivity changes caused by xenon poisoning, burnup, etc. are still compensated by boron tuning systems. Xenon is time-scale and time-scale fading, and in order to compensate for the slow reactivity changes caused by xenon, repeated boronation and dilution of the primary coolant are still required during the usual daily load tracking.
In summary, the above load tracking requires frequent dilution and boronization of the primary coolant, and boron adjustment can result in the following disadvantages: 1) a large amount of boron waste liquid to be treated is generated, and the operation cost is increased; 2) near the end of the life, boron adjustment can generate waste liquid which is several times more than that at the beginning of the life due to low boron concentration, so that a waste liquid treatment system of a nuclear power plant cannot bear the waste liquid to lose load tracking capability; 3) boron adjustment can generate a large amount of radioactive waste liquid, and the treated waste liquid has low radioactivity and still brings certain pressure to environmental protection; 4) the boron adjustment operation is manually carried out, which increases the burden of operators.
To solve the above problems, westinghouse corporation in the united states of america realized no adjustment of boron load following operation in reference 1 (method and method of controlling nuclear reactor to reduce boron concentration adjustment during load change [ invention patent ], 81108319, 1981), improving the economy and operational flexibility of the reactor. However, this mode (MSHIM mode) also requires two sets of control rod sets to be inserted into the core at base load operation as at load following operation, and requires a time transition of about one or two days to wait for the xenon distribution to approach rebalancing at the time of switching from base load operation to load following operation. In the China Central and China Wide Nuclear group, an irregular boron load tracking mode (BTP mode) is also researched in a comparison document 2 (Magz volume, Yao Zeohua. M310 pressurized water reactor improvement, irregular boron load following research [ journal ]. Nuclear science and engineering, 2004, 4: 294-300), but in order to enable axial power deviation during load tracking not to exceed the left boundary of an operation ladder diagram all the time, the axial fuel consumption gradient of a reactor core needs to be constructed manually, the construction method is that a power compensation rod group is required to be inserted into the reactor core besides a temperature regulation rod group during the operation of a base load, namely two sets of control rod groups are still inserted into the reactor core all the time.
In order to solve the problem that xenon transient state easily causes large axial power oscillation amplitude and is difficult to control after base load operation is switched to load tracking operation, the two non-modulated boron load tracking implementation methods (MSHIM and BTP modes) require that two sets of control rod groups are inserted into a reactor core when the base load operation is carried out, so that the defects of uneven fuel consumption, increased control rod injection quantity, more control rod absorber fuel consumption, increased control rod driving mechanism load and the like are caused. The invention provides a new method for realizing the load tracking without regulating boron, which only needs to insert a group of control rods into a reactor core during the operation of base load and avoids the defects.
Disclosure of Invention
Aiming at the problems that the existing method for realizing the load tracking without adjusting boron requires that two sets of control rod groups are inserted into the reactor core when the base load runs, so that the defects of uneven fuel consumption, increased control rod injection amount, more control rod absorber fuel consumption, increased control rod driving mechanism load and the like are caused.
In order to solve the problems, the implementation method of the nuclear reactor load tracking provided by the invention solves the problems through the following technical key points: a method for realizing load tracking of a nuclear reactor adopts two sets of relatively independent control rod sets for reactivity and axial power offset power control of the nuclear reactor;
the two sets of control rod groups are respectively a T rod group and a K rod group, wherein the K rod group consists of a plurality of beams of black rods, and the T rod group comprises a plurality of beams of gray rods and black rods;
during base load operation of the nuclear reactor, only the K rod sets are inserted into the core, and the insertion depth of the K rod sets is greater than or equal to the bite amount plus 24 steps;
during load following operation of the nuclear reactor, the T-bar set and the K-bar set are each inserted into the core.
Specifically, in the prior art, a magnetic lifting type control rod driving mechanism is generally adopted as the pressurized water reactor control rod driving mechanism. The above bite is generally the minimum number of insertion steps for the control rod to achieve a differential value of 2.5 pcm/step, i.e., one step is the alternate engagement of a tooth by the finger and the groove in the annular rod of the drive rod member. The black rod is a control rod with strong neutron absorption capacity, and the gray rod is a control rod with weak neutron absorption capacity.
. When the base load operates, the insertion depth of the K rod group is set to be larger than or equal to the biting amount plus 24 steps, namely a certain balance xenon axial gradient and a fuel consumption axial gradient are introduced, and a larger extraction space is reserved for the K rod group to enable the K rod group to have stronger capability of compensating power downward deviation, so that the base load operation is switched to the load tracking operation without causing larger xenon-caused axial power oscillation, and the problem that the axial power deviation is difficult to control when the base load is not in boron load tracking transition can be effectively solved.
Specifically, during base load operation:
only the K rod groups are inserted into the reactor core;
through the change of the insertion depth of the K rod group, the average temperature of the core coolant is controlled by the K rod group;
through the change of the insertion depth of the K rod group, the axial power deviation of the reactor core and smaller reactivity change are also controlled by the K rod group;
the stepwise adjustment of soluble boron compensates for the burn-up induced reactivity change to bring the K-bar set back into the operating range.
During load tracking operation:
the T rod group and the K rod group are inserted into the reactor core;
the average temperature of the core coolant is controlled by the T-bar group, and therefore, the reactivity change caused by power, xenon poison and the like is controlled;
the axial power excursion is controlled by the K rod set;
the stepwise adjustment of soluble boron compensates for the burn-up induced reactivity change to bring the K-bar and T-bar groups back into the operating range.
By adopting the method, the defect that excessive control rods are inserted into the reactor core when the base load is operated is avoided, and the load tracking operation can be started at any time without transition days when the load tracking operation is switched, so that the nuclear power unit has stronger maneuverability;
the boron regulation operation is not required to be frequently carried out in the load tracking process, the wastewater treatment cost is reduced, and the load tracking capacity is correspondingly prolonged from 85% of the service life to 95% of the service life;
for the base load operation condition, the method only needs to insert a group of control rods into the reactor core, and the control power control mode of the control rods is consistent with the traditional control modes (A mode and G mode), so that the technology is mature, and the safe operation of the nuclear power station is facilitated.
The method avoids the defects of uneven fuel consumption, increased control rod injection amount, more control rod absorber fuel consumption, increased control rod drive mechanism load and the like caused by excessive control rod inserted into the reactor core during base load operation.
The further technical scheme is as follows:
in order to reduce the disturbance of T rod groups to the axial power excursion of the reactor core during the load following operation of the nuclear reactor, the T rod groups are divided into a plurality of groups, and each group of the T rod groups comprises a plurality of rod bundles;
during load following operation of the nuclear reactor, groups of the T-bar sets are sequentially inserted into or withdrawn from the core;
during the insertion and extraction process, there are overlapping steps between adjacent groups.
In order to reduce disturbance of the T-bar groups to axial power offset of a reactor core during load tracking operation of the nuclear reactor, control rods in part of the T-bar groups are gray rods, and control rods in the rest of the T-bar groups are black rods;
during load following operation of the nuclear reactor, in the insertion process, groups that are all black rods are inserted followed by groups that are all gray rods; in the proposed process, groups that are all black bars are proposed in order before groups that are all gray bars. In the scheme, the specific inserting process and the specific extracting process are set during the load tracking operation of the nuclear reactor, and aim to reduce the disturbance of the T-bar group to the axial power deviation of the reactor core, and the T-bar group is set to comprise black bars, so that the reactor core can obtain higher power regulation capacity through the T-bar group.
In order to realize the realization scheme that the axial power offset disturbance is small and the power tracking response is fast when the reactor adopting the method is used for load tracking: when the adjacent groups are gray rods and gray rods, the overlapping of the control rods of the adjacent groups is between one fourth of the rod length and one half of the rod length; when the adjacent groups are gray rods and black rods, the overlapping of the control rods of the adjacent groups is less than one quarter of the rod length.
As a specific implementation manner of the black rod, the black rod is a silver-indium-cadmium rod.
As a specific implementation manner of the gray rod, the gray rod is any one of the following two manners: a mixed structure consisting of a tungsten rod, a stainless steel rod and a silver-indium-cadmium rod.
The invention has the following beneficial effects:
the method provided by the invention is different from the conventional strategy for realizing irregular boron load tracking aiming at a pressurized water reactor nuclear power plant, and the strategy only needs one group of control rods to be inserted into the reactor core during the base load operation period, thereby avoiding a series of defects caused by excessive control rods being inserted into the reactor core. The key point of the technology is that the group of control rods are slightly inserted into the reactor core deeper than the traditional mode, and a certain balance xenon axial gradient and a certain fuel consumption axial gradient are artificially introduced, so that the axial xenon oscillation amplitude of the reactor core is smaller when the load tracking mode is switched, the group of control rods are used for controlling the axial power offset during the load tracking period, and a larger proposed space is reserved to enable the group of control rods to have stronger capability of compensating the downward power offset, so that the axial power offset of the reactor core can be controlled near a reference value only by a control rod, the problem of the tracking transition from the base load to the load is solved, and a transition day is not needed. When the load tracking operation is converted, the control tasks of the control rods are switched, and two control rod sets are inserted into the reactor core instead. During the load tracking operation, the reactivity change caused by the power and xenon change is compensated by the control rod, and the non-regulated boron load tracking is realized. Only the reactivity changes due to core burnup are compensated by adjusting boron, as is the case for base load operation.
Specifically, the method comprises the following steps:
when the power plant adopting the method is quickly switched from the base load operation to the load tracking operation, the oscillation amplitude of the axial power of the reactor core is small, the axial power deviation of the reactor core can be controlled in an operation band by the K rod group in the operation range of the K rod group, and the load tracking operation can be started at any time without transition days.
The method does not need to frequently adjust boron in the load tracking process, reduces the wastewater treatment cost, and correspondingly prolongs the load tracking capacity from 85 percent of the service life to 95 percent of the service life.
For the base load operation condition, the method only needs to insert a group of control rods into the reactor core, and the control power control mode of the control rods is consistent with the traditional control modes (A mode and G mode), so that the technology is mature, and the safe operation of the nuclear power station is facilitated;
the method avoids the defects of uneven fuel consumption, increased control rod injection amount, more control rod absorber fuel consumption, increased control rod drive mechanism load and the like caused by excessive control rod inserted into the reactor core during base load operation.
Drawings
FIG. 1 is a core control rod arrangement diagram of an embodiment of the method for implementing nuclear reactor load tracking according to the present invention, wherein corresponding letters indicate that corresponding bundles are arranged therein. The T rod group is composed of 3 groups of gray rods (T1, T2, T3) and 2 groups of black rods (T4, T5), the K rod group is composed of 1 group of black rods (K), and the S rod group is composed of 2 groups of black rods (S1, S2);
FIG. 2 is a diagram of a simulation result reflecting the variation of relative power with time in a typical daily load tracking operation simulation, according to an embodiment of a method for implementing nuclear reactor load tracking provided by the present invention;
FIG. 3 is a diagram of a simulation result reflecting the change of boron concentration with time in a typical daily load tracking operation simulation, according to an embodiment of a method for implementing nuclear reactor load tracking provided by the present invention;
FIG. 4 is a diagram of a simulation result reflecting the variation of the average xenon concentration with time in a typical daily load tracking operation simulation, illustrating an embodiment of a method for implementing nuclear reactor load tracking according to the present invention;
FIG. 5 is a diagram of a simulation result reflecting the change of xenon axial shift with time in a typical daily load tracking operation simulation, according to an embodiment of a method for implementing nuclear reactor load tracking provided by the present invention;
FIG. 6 is a diagram of a simulation result reflecting the variation of the number of insertion steps of a T-bar set with time in a typical daily load tracking operation simulation, according to an embodiment of a method for implementing nuclear reactor load tracking provided by the present invention;
FIG. 7 is a diagram of a simulation result reflecting the variation of insertion steps of K rod groups with time in a typical daily load tracking operation simulation, according to an embodiment of a method for implementing nuclear reactor load tracking provided by the present invention;
fig. 8 is a diagram of a simulation result reflecting a change of an axial power deviation with time in a typical daily load tracking operation simulation, according to a specific embodiment of the method for implementing nuclear reactor load tracking provided by the present invention.
In which fig. 2 to 8 show 100% -50% daily load tracking of 12-3-6-3 for 4 consecutive days starting from the base load (i.e. in 24 hours of each day, it takes 3 hours to linearly reduce the power from 100% to 50%, then to maintain 50% power for 6 hours, then to linearly increase the power from 50% to 100% for 3 hours, and finally to maintain 100% power for 12 hours). In the above figures, during the load tracking process, the relevant parameters of the core change actively or passively with time.
Detailed Description
The present invention will be described in further detail with reference to the following examples, but the present invention is not limited to the following examples:
example 1:
as shown in fig. 1 to 8, this embodiment provides a specific implementation scheme based on the implementation method for nuclear reactor load tracking, in this implementation scheme, the corresponding nuclear reactor is a dual-loop pressurized water reactor, and the core is composed of 121 fuel assemblies. FIG. 1 shows a typical core control rod arrangement using 45 bundles of control rods, 33 of which are black body control rods and 12 of which are gray body control rods. The shutdown rod set is an S-rod set and is used for ensuring that the reactor has enough shutdown allowance at any power level. The control rods and shutdown rods were 225 steps in length. The control rod set comprises a K rod set and a T rod set. During base load operation, only the K rod sets are inserted into the core, controlling the core coolant mean temperature and axial power excursions. During load following operation, both K-rod and T-rod groups are inserted into the core, the K-rod group controlling only axial power excursions, and the T-rod group compensating for power feedback and transient xenon equivalent induced reactivity changes by controlling core coolant average temperature. The rods of each group in the T rod group are inserted in a drawing way according to a certain sequence and overlapping steps, the inserting sequence is T1, T2, T3, T4 and T5, the sequence is T5, T4, T3, T2 and T1, the overlapping step among the gray rods of each group is 80 steps, and the overlapping step among the gray rods and the black rods and between the black rods of two groups is 12 steps.
During base load operation, keeping the K rod set inserted near the +24 bite, the coolant average temperature is controlled by the individual K rod sets, and the operator can adjust the boron concentration to change the position of the K rod sets to ensure that the axial power offset is near the reference value, similar to conventional control strategies. In preparation of load tracking operation, control division of the control rod sets is switched and set to be an automatic control mode, then boron is adjusted to drive the T rod sets into the reactor core to a certain depth (based on that the T rod sets can smoothly return to full power by lifting in the load tracking process), and load tracking operation can be started immediately without transition days. When the load tracking is started, the average temperature of the coolant of the reactor is increased due to the reduction of the load of the steam turbine, the T rod group is automatically inserted downwards, and the power of the reactor is reduced so as to maintain the average temperature of the coolant to be close to a set value; the power of the reactor is reduced to cause xenon transient change, when the power reaches a low-power operation platform, negative reactivity is introduced by xenon accumulation, and the T rod group is automatically and slowly lifted out; after the xenon peak, the T-bar set will be slowly inserted again. On the contrary, when the load of the steam turbine is increased, the average temperature of the coolant of the reactor is reduced, the T rod group is automatically lifted, and the power of the reactor is improved so as to maintain the average temperature of the coolant to be close to a set value; when the high-power operation platform is reached, positive reactivity is introduced due to xenon consumption, and the T rod group is slowly inserted into the reactor core; this is repeated until base load operation is returned and xenon equilibrium is reached.
Figures 2 to 8 show typical daily load following procedures at the end of the 95% life cycle of the above two-loop pressurized water reactor. During the base load operation before load tracking, the K rod group is kept inserted at the position of +24 steps of biting amount, and the load tracking is started immediately after the T rod group is driven into the reactor core by reducing the boron concentration. Δ Iref (axial power deviation Δ I reference value) during load tracking remains the same as that at the base load, and it can be seen that Δ I is effectively controlled and can be always maintained within a control dead band narrower than the operating band (the control dead band during load tracking can be set to Δ Iref ± 3, and the control dead band for base load operation can be set to Δ Iref ± 1). With this strategy, the xenon axial offset fluctuates only within a small range of-1.5% to + 1.5%, and the K-bar set does not have to be completely lifted out of the stack nor inserted too deeply. With this strategy, there is no Δ I control difficulty in returning the load tracking from low power to full power and maintaining for 12 hours, and it is clear that maintaining full power operation for a longer time is less difficult, i.e., it is smooth to transition directly from load tracking operation back to base load operation. In conclusion, by using the strategy, the fast reactivity change and the axial power distribution can be adjusted only by the control rod during the load tracking, the boron concentration does not need to be adjusted unless the burnup effect is compensated, and the non-regulated boron load tracking is realized.
The foregoing is a more detailed description of the present invention in connection with specific preferred embodiments thereof, and it is not intended that the specific embodiments of the present invention be limited to these descriptions. For those skilled in the art to which the invention pertains, other embodiments that do not depart from the gist of the invention are intended to be within the scope of the invention.
Claims (6)
1. A method for realizing load tracking of a nuclear reactor is characterized in that two sets of relatively independent control rod sets are adopted for reactivity and axial power excursion power control of the nuclear reactor;
the two sets of control rod groups are respectively a T rod group and a K rod group, wherein the K rod group consists of a plurality of beams of black rods, and the T rod group comprises a plurality of beams of gray rods and black rods;
during base load operation of the nuclear reactor, only the K rod sets are inserted into the core, and the insertion depth of the K rod sets is greater than the bite amount plus 24 steps;
during load following operation of the nuclear reactor, the T-bar set and the K-bar set are each inserted into the core.
2. The method of claim 1, wherein the T-rod groups are in groups, and each group of the T-rod groups comprises a plurality of bundles;
during load following operation of the nuclear reactor, groups of the T-bar sets are sequentially inserted into or withdrawn from the core;
during the insertion and extraction process, there are overlapping steps between adjacent groups.
3. The method of claim 2, wherein the control rods in some of the groups of T-rod groups are gray rods, and the control rods in the other groups are black rods;
during load following operation of the nuclear reactor, in the insertion process, groups that are all black rods are inserted followed by groups that are all gray rods; in the proposed process, groups that are all black bars are proposed in order before groups that are all gray bars.
4. A method as claimed in claim 3, wherein when adjacent groups are gray rods and gray rods, the overlap of control rods of adjacent groups is between one quarter and one half of the length of the rods; when the adjacent groups are gray rods and black rods, the overlapping of the control rods of the adjacent groups is less than one quarter of the rod length.
5. A method for implementing load tracking of a nuclear reactor as claimed in any one of claims 1 to 4, wherein said black rods are silver-indium-cadmium rods.
6. A method for implementing nuclear reactor load tracking according to any one of claims 1 to 4, wherein said gray rods are in any one of the following two ways: a mixed structure consisting of a tungsten rod, a stainless steel rod and a silver-indium-cadmium rod.
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| CN113793707B (en) * | 2021-08-20 | 2022-12-09 | 西安交通大学 | Irregular boron load tracking operation and control method for pressurized water reactor nuclear power plant |
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