CN108416135B - Method and device for fitting emergency protection value by measuring single group of rod values - Google Patents
Method and device for fitting emergency protection value by measuring single group of rod values Download PDFInfo
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Abstract
The invention discloses a method for fitting an emergency protection value by measuring values of a single group of rods, which comprises the following steps: obtaining the sum of calculated values of integral values of each of the n control rod groups
Obtaining a calculated value EP of the emergency protection value when no stick is stuckcal(ii) a Obtaining the sum of actual measurements of the integrated value of each of the n control rod groups
Calculating a simulation test value according to the formula (7)
To be used as an actual measurement value EP of emergency protection valueexp：
The invention also discloses a method for fitting the value of the single group of measured rods to the value of the emergency protectionProvided is a device. By adopting the method or the device, the measured value of the emergency protection value can be rapidly simulated according to the measured control rod integral value.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor physical test methods, and particularly relates to a method and a device for fitting an emergency protection value by measuring values of a single group of rods.
Background
During the fuel refueling starting period of the nuclear power plant, an emergency protection value measurement test needs to be carried out according to the requirements of a test outline.
In an emergency protection value measurement test, positive and negative responses are introduced by lifting the 10 th group of control rods, so that the reactive power is lifted to a level close to 1% Nnom (rated power), a reactor operator manually executes an emergency protection button, all other control rods except a clamped rod bundle fall to the bottom of a reactor core, and the clamped rod bundle also falls to the bottom of the reactor core after recording data for 1 minute, so that test recording is completed.
When the emergency protection value measurement test is carried out, the time consumption is long because boron dilution operation needs to be carried out in the reactor core, and therefore the overhaul time is prolonged. In order to reduce the overhaul time, it is desirable to cancel the emergency protective value measurement test and obtain a measurement value of the emergency protective value based on the existing test results. At present, a more ideal method is that a dynamic rod carving method is adopted to carry out a control rod value measurement test, and then a measurement value of the emergency protection value is calculated in a simulation mode according to the measured integral values of all groups of rods, so that the traditional emergency protection value measurement test can be cancelled.
At present, the power plant which is mainstream internationally generally adopts a dynamic rod-carving method to realize the rapid measurement of the value of the control rod, the dynamic rod-carving method does not need to carry out the adjustment of the concentration of soluble boron in the test process, only one group of control rods needs to be operated each time, the method is safer than the traditional test method, and the overhaul time of the nuclear power plant can be obviously shortened by adopting the method. Therefore, the domestic nuclear power plant gradually adopts the dynamic rod-carving technology to replace the traditional test mode. For example, in 2014, Jiangsu Nuclear Power Co., Ltd in 11 months, submitted an application report (Suzhou Kao [ 2014 ] 472) adopting WWER (Tianwan 1, No. 2 unit heap type) advanced dynamic rod carving technology to NNSA (nuclear safety agency), and the application contents include:
1. the WWER advanced dynamic rod carving technology is adopted to replace a boron regulation method to measure the control rod calculus value;
2. and (3) increasing the measurement range of the control rod set, measuring 1-10 control rod sets, and simultaneously canceling the traditional emergency protection value measurement test.
Next, the gulf nuclear power plant (Jiangsu nuclear power plant) performed an advanced engraving synchronization verification test during the refueling start period of T208 (No. 2 unit overhaul for 8 times)/T109 (No. 1 unit overhaul for 9 times). NNSA approval was obtained at 29/8/2016, and the advanced rod carving technique was first implemented by the T209 overhaul instead of boron regulation.
After the advanced dynamic rod carving technology is implemented, the integral value of 1-10 control rod groups can be measured, and R is usedi exp(i is 1-10), and then the measured value of the emergency protection value can be simulated and calculated by a reasonably rigorous mathematical method and the integral value of each group of control rods, and the EP is used forexpAnd (4) showing. Therefore, on the premise of carrying out an advanced rod engraving test, the traditional emergency protection value measurement test is cancelled, the overhaul time is shortened, the annual average capacity factor of the unit is increased, and the economical efficiency of the power station is improved.
However, how to calculate the measured value of the emergency protection value according to the measured integral values of the control rods of each group is complicated in the current calculation method, so that the calculation takes more time, and the actual measured value of the emergency protection value finally obtained by simulation after calculation by adopting the calculation methods is not necessarily accurate, and the fundamental theory remains to be questioned.
Disclosure of Invention
The present invention provides a method and an apparatus for fitting an emergency protection value by measuring a single group of rod values, which can rapidly simulate an actual measurement value of the emergency protection value according to a measured control rod integral value, thereby obtaining a simulated test value, and the simulated test value has a small error compared with the actual measurement value.
In order to solve the technical problems, the invention adopts the following technical scheme:
a method of fitting an emergency protective value from a measured single set of wand values, comprising the steps of:
obtaining the sum of calculated values of integral values of each of the n control rod groups
Obtaining a calculated value EP of the emergency protection value when no stick is stuckcal；
Obtaining the sum of actual measurements of the integrated value of each of the n control rod groups
Calculating a simulation test value according to the following formula
And using the value as the measured value EP of the emergency protection valueexp：
Preferably, the sum of the calculated values of the integrated value of each of the n control rod groups is obtained
The method specifically comprises the following steps:
computing n control rod groups by using computing program packageThe calculated value of the integral value of each control rod group is added to obtain the sum of the calculated values of the integral values of the control rod groups
Preferably, the calculated value EP of the emergency protection value without the stick is obtainedcalThe method specifically comprises the following steps: calculating a calculated value EP of the emergency protection value without the clamping rod by adopting a calculation program packagecal。
Preferably, the sum of the actual measured values of the integrated value of each of the n control rod groups is obtained
The method specifically comprises the following steps:
measuring the actual measurement value of the integral value of each of the n control rod groups, and adding the measured actual measurement values of the integral values of the control rod groups to obtain the sum of the actual measurement values of the integral values of the control rod groups
More preferably, the temperature deviation between the coolant temperature of the core at the time of measurement and the coolant temperature of the core at the time of calculation is within ± 3 ℃, and the position deviation between the position of the inserted control rod group and the position of the inserted control rod group at the time of calculation is within ± 3.5%.
It is further preferred that the actual measurement of the integrated value of each of the n control rod groups is measured using a dynamic carving rod technique.
Accordingly, the present invention also provides an apparatus for fitting an emergency protective value from a measured single set of rod values, comprising:
a first acquisition unit for acquiring the sum of calculated values of integral values of each of the n control rod groups
A second acquisition unit for acquiring a calculated value EP of the emergency protection value without the stickcal；
A third obtaining unit for obtaining the sum of actual measurement values of the integral value of each of the n control rod groups
A calculating unit for calculating a simulation test value according to the following formula (7)
And using the value as the measured value EP of the emergency protection valueexp：
Preferably, the first acquisition unit includes:
the first calculation program package module is used for calculating the calculation value of the integral value of each control rod group in the n control rod groups;
the first summation module is used for adding the calculated values of the integral values of the control rod groups calculated by the first calculation program package module to obtain the sum of the calculated values of the integral values of the control rod groups
Then the obtained calculated values of the integral values of all the control rod groups are summed
Sent to the calculation unit.
Preferably, the second acquisition unit comprises a second calculation program package module for calculating a calculation value EP of the emergency protection value without the stick clipcalAnd calculating the value EPcalSent to the calculation unit.
Preferably, the third acquisition unit includes:
a third measurement module for measuring an actual measurement of the integrated value of each of the n control rod groups;
a third summation module for summing the actual measurement values of the integrated value of each control rod group measured by the third measurement module to obtain the sum of the actual measurement values of the integrated value of each control rod group
Then the obtained actual measured values of the integral values of all the control rod groups are summed
Sent to the calculation unit.
When the method or the device is used for calculating the measured value of the emergency protection value, the rod value of each control rod group can be measured by the advanced dynamic rod engraving technology to reduce the measurement time of the control rod value, and then the measured value of the emergency protection value is calculated by simulation of the method or the device, so that the emergency protection value measurement test can be cancelled on the premise of carrying out the advanced rod engraving test, the overhaul time is greatly reduced, the annual average capacity factor of the unit is increased, and the economical efficiency of a power station can be increased finally.
The method is suitable for all the measured values used for calculating the emergency protection value in the pressurized water reactor nuclear power station.
Drawings
FIG. 1 is a flow chart of a method of fitting an emergency protective value from measured values of a single set of sticks according to an embodiment of the present invention 1;
fig. 2 is a schematic structural diagram of an apparatus for fitting an emergency protective value by measuring values of a single set of rods according to embodiment 2 of the present invention.
Detailed Description
The technical solution of the present invention will be described clearly and completely with reference to the accompanying drawings, and it should be understood that the described embodiments are a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be obtained by a person skilled in the art without any inventive step based on the embodiments of the present invention, are within the scope of the present invention.
The inventor of the invention obtains the following theories through research on a WWER reactor type nuclear power station:
among them, since the WWER heap type usually requires the use of a matching calculation package at the time of design, some parameters can be calculated using the calculation package. For example, the KASKAD computing package developed by russian coulter research institute may be used.
And the following parameters can be calculated using the KASKAD calculation package:
Ri cal(i-1-n) 1-n sets of calculated values of the integrated value of each control rod set, wherein n > 1;
EPcaland calculating the emergency protection value without the clamping rod.
Measuring the integral value of each control rod group in the 1-n groups of control rod groups (for example, preferably, the measurement can be carried out by adopting an advanced dynamic rod carving technology), and obtaining the actual measurement value R of the integral value of each control rod group in the 1-n groupsi exp(i＝1～n)。
Since the value of each control rod group contributes to the emergency protection value, but due to the interference effect between the control rod groups, the emergency protection value is not equal to the sum of the integral values of the control rod groups, if the weighting factor of each control rod group is thetaiThe following parametric relationships can be obtained:
then the process of the first step is carried out,
wherein the content of the first and second substances,
an equivalent weight factor representing the calculated value;
similarly, the measured value of the emergency protection value also has the following parameter relationship:
then the process of the first step is carried out,
wherein the content of the first and second substances,
an equivalent weight factor representing the measured value.
The equal sign sides of the formula (3) and the formula (1) are divided as follows:
it is thus possible to obtain:
if the state parameters used in the calculation by adopting the KASKAD calculation program package are close to the state parameters measured in the real test, then
And
approximately equal; if the closer the state parameter used in the calculation is to the state parameter measured in the real experiment,
the closer the ratio is to 1, this is easily done, as this is required by the test outline. Wherein the state parameters used in the calculation are specified in a test program, and the test outline requires a real testThe state parameters measured on site during the test should be as consistent as possible with the state parameters specified in the test program, and only small differences between the two can exist. In general, the condition parameters that can affect the measurements are typically two, one being the coolant temperature of the core and the other being the location where the inserted set of control rods is located. Therefore, the requirement of the test outline can be satisfied by ensuring that the temperature deviation between the coolant temperature of the core and the coolant temperature of the core at the time of calculation is as small as possible and the positional deviation between the position of the inserted control rod group and the position of the inserted control rod group at the time of calculation is as small as possible at the time of measurement.
For example, the coolant temperature of the core is 280 ℃ in calculation, the 10 th group of control rod groups (namely, the inserted control rod groups) is at the position of 80%, and by referring to the starting physical test report of a plurality of cycles of a plurality of units, the coolant temperature is between 280 ℃ and 282 ℃ in measurement, the 10 th group of control rod groups is at the position of 77% to 83%, that is, the coolant temperature deviation of the core is less than or equal to 2 ℃, the position deviation of the control rod groups is less than or equal to 3%, and the deviation is very small. Therefore, equation (6) can be simplified as:
in the 3 parameters to the right of the approximate number of formula (7), where Ri calAnd EPcalCan be obtained by calculation ofi expCan be obtained by experimental measurement and are all known numbers. The emergency protective value calculated by this combined measurement and mathematical method, called the simulation test value, is used
And (4) showing. After repeated experiments, the inventor finds that the relative deviation between the simulation test value calculated by using the formula (7) and the real measurement value of the verification test is usually not more than +/-5% (the deviation is within the range of the test acceptance criterion), that is, the difference between the simulation test value and the actual measurement value of the emergency protection value is very small, so that the simulation test value and the actual measurement value of the emergency protection value can be used for reducing the emergency protection valueMeasured value EP equivalent to emergency protection valueexp。
The inventor finds, through a plurality of experiments, that the above theoretical method is not limited to be used only in WWER reactor type nuclear power plants, but is applicable to all pressurized water reactor nuclear power plants.
According to the above theory, the present invention discloses a method for fitting an emergency protection value by measuring a single set of rod values, comprising the steps of:
obtaining the sum of calculated values of integral values of each of the n control rod groups
Obtaining a calculated value EP of the emergency protection value when no stick is stuckcal；
Obtaining the sum of actual measurements of the integrated value of each of the n control rod groups
Calculating a simulation test value according to the following formula
And using the value as the measured value EP of the emergency protection valueexp：
Accordingly, the present invention also provides an apparatus for fitting an emergency protective value from a measured single set of rod values, comprising:
a first acquisition unit for acquiring the sum of calculated values of integral values of each of the n control rod groups
A second acquisition unit for acquiring a calculated value EP of the emergency protection value without the stickcal；
A third acquisition unit forFor obtaining the sum of actual measured values of the integrated value of each of the n control rod groups
A calculating unit for calculating a simulation test value according to the following formula (7)
And using the value as the measured value EP of the emergency protection valueexp：
Example 1:
the method for fitting the emergency protection value by measuring the single group rod value in the embodiment is mainly applied to a pressurized water reactor nuclear power station, and particularly applied to a WWER reactor type nuclear power station (such as a gulf nuclear power station) in the embodiment.
As shown in fig. 1, in this embodiment, the method for calculating the emergency protection value mainly includes the following steps:
s1, obtaining the sum of the calculated values of the integral value of each control rod group in the n control rod groups
The selection of the number of the control rod sets can be set according to the specific situation of the nuclear power plant to which the method is applied. In this embodiment, n is set to 10, that is, 10 sets of control rods are used.
Specifically, a calculation value R of the integral value of each control rod group in 1-10 control rod groups is calculated by adopting a calculation program packagei cal(i is 1-10), and calculating the calculated value R of the integral value of 10 control rod groupsi calAdding up to obtain the sum of calculated values of integral value of each control rod group
In this embodiment, it is preferable to calculate the calculated value R of the integral value of each control rod group of 1 to 10 control rod groups by using kaskaskad calculation package developed by russian coulter research institutei cal(i is 1 to 10). Of course, other core calculation packages may be used to perform the calculations.
The above calculation process is prior art in the field and is not described in detail here.
S2, obtaining a calculated value EP of the emergency protection value when no stick is stuckcal。
In this embodiment, the calculation value EP of the emergency protection value without the stick is preferably calculated by using the KASKAD calculation package developed by russian coulter research institutecal. Of course, other core calculation packages may be used to perform the calculations.
The above calculation process is prior art in the field and is not described in detail here.
S3, obtaining the sum of the actual measured values of the integral value of each control rod group in the n control rod groups
In this embodiment, the actual measurement value is specifically the value of the integral measured for each of the 10 control rod groups
And then measuring the actual measurement value of the integral value of 1-10 control rod groups
Added to obtain the sum of the actual measured values of the integrated values of the 10 control rod groups
The actual measurement of the integrated value of each of the 10 control rod groups using dynamic inscribing technique is preferably used in this embodimentAnd (6) measuring the values. That is, before the actual measurement value of the emergency protection value is calculated by using the method, the nuclear power plant adopts the WWER advanced dynamic rod carving technology to measure the control rod integral value, so as to measure the actual measurement value of the integral value of each of 10 control rod groups, and further obtain the sum of the actual measurement values of the integral value of the 10 control rod groups
When the control rod integral value is measured, the temperature deviation between the coolant temperature of the reactor core and the coolant temperature of the reactor core during calculation is ensured to be as small as possible, and the position deviation between the position of the inserted 10 th group of control rod groups and the position of the 10 th group of control rod groups during calculation is ensured to be as small as possible.
Preferably, the temperature deviation between the coolant temperature of the core at the time of measurement and the coolant temperature of the core at the time of calculation is within ± 3 ℃, and the position deviation between the position of the inserted control rod group and the position of the inserted control rod group at the time of calculation is within ± 3.5%.
Of course, instead of using the dynamic rod carving technique to obtain the actual measurement value of the integrated value of each control rod group, other methods may be used to obtain the actual measurement value of the integrated value of each control rod group, for example, a conventional actual measurement method (boron modulation method) may be used to obtain the actual measurement value of the integrated value of each control rod group.
The above steps S1, S2, and S3 are not in order.
S4, calculating the simulation test value according to the following formula
And using the value as the measured value EP of the emergency protection valueexp。
Specifically, the values calculated in step S1, step S2, and step S3 are respectively
The value of (2) is substituted into the following formula (8), thereby obtaining a simulation test value
According to the theory, the obtained simulation test value is calculated
Measured value EP of emergency protection valueexpThe deviation therebetween is small, and therefore, the simulation test value to be obtained according to the formula (9)
Measured value EP equivalent to emergency protection valueexp. Therefore, the method in the embodiment can simulate and calculate the measured value EP of the emergency protection valueexpThus, the emergency protection value measurement test is not needed.
Taking the starting physical test performed during two overhauls (i.e., overhauls T109 and T209) of the nuclear power plant in the gulf of the field as an example, the following parameters were obtained as shown in table 1:
TABLE 1
Wherein, in Table 1
Calculated according to the above-mentioned method in the present example according to the formula (7), EP in Table 1expThe measured value of the emergency protection value is obtained through actual measurement during the two times of overhaul. Slave watchAs can be seen from the test results obtained in 1, the simulation test values
Measured value EP of emergency protection valueexpThe deviation is small, the requirement that the relative deviation does not exceed +/-5 percent is met, and the acceptance criterion of the test is completely met.
Therefore, by using the method in the embodiment, the measured value of the emergency protection value can be obtained through rapid simulation calculation according to the measured rod value of each control rod group, so that the emergency protection value measurement test can be cancelled, the overhaul time can be greatly reduced, the annual average capacity factor of the unit can be increased, and the economical efficiency of the power station can be increased finally.
Example 2:
as shown in fig. 2, the apparatus for fitting the emergency protective value by measuring the value of a single set of rods in the present embodiment includes:
a first acquisition unit for acquiring the sum of calculated values of integral values of each of the n control rod groups
A second acquisition unit for acquiring a calculated value EP of the emergency protection value without the stickcal；
A third obtaining unit for obtaining the sum of actual measurement values of the integral value of each of the n control rod groups
A calculating unit for calculating a simulation test value according to the following formula (7)
And using the value as the measured value EP of the emergency protection valueexp：
In this embodiment, it is preferable that the first obtaining unit includes a first computation package module and a first summing module,
the first calculation program package module is used for calculating a calculated value of the integral value of each control rod group in the n control rod groups and sending the calculated value to the first summation module;
the first summation module is used for adding the calculated values of the integral values of the control rod groups calculated by the first calculation program package module to obtain the sum of the calculated values of the integral values of the control rod groups
Then the obtained calculated values of the integral values of all the control rod groups are summed
Sent to the calculation unit.
The second acquisition unit comprises a second calculation program package module for calculating a calculation value EP of the emergency protection value when no stick is stuckcalAnd calculating the value EPcalSent to the calculation unit.
Preferably the third acquisition unit comprises a third measurement module and a third summation module,
the third measuring module is used for measuring the actual measured value of the integral value of each control rod group in the n control rod groups and sending the actual measured value to the third summing module;
a third summation module for summing the actual measurement values of the integrated value of each control rod group measured by the third measurement module to obtain the sum of the actual measurement values of the integrated value of each control rod group
Then the obtained actual measured values of the integral values of all the control rod groups are summed
Sent to the calculation unit.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (9)
1. A method of fitting an emergency protective value from a measured single set of wand values, comprising the steps of:
obtaining the sum of calculated values of integral values of each of the n control rod groups
Obtaining a calculated value EP of the emergency protection value when no stick is stuckcal；
Obtaining the sum of actual measurements of the integrated value of each of the n control rod groups
Calculating a simulation test value according to the following formula
And using the value as the measured value EP of the emergency protection valueexp：
2. The method of claim 1, wherein the sum of the calculated values of the integrated value for each of the n control rod groups is obtained
The method specifically comprises the following steps:
computing n pieces by using computing program packageThe calculated value of the integral value of each of the control rod groups is added to obtain the sum of the calculated values of the integral values of the control rod groups
Obtaining a calculated value EP of the emergency protection value when no stick is stuckcalThe method specifically comprises the following steps:
calculating a calculated value EP of the emergency protection value without the clamping rod by adopting a calculation program packagecal。
3. The method of claim 2, wherein the sum of actual measurements of the integrated value of each of the n control rod groups is obtained
The method specifically comprises the following steps:
measuring the actual measurement value of the integral value of each of the n control rod groups, and adding the measured actual measurement values of the integral values of the control rod groups to obtain the sum of the actual measurement values of the integral values of the control rod groups
4. The method of claim 3, wherein the measuring is performed such that the temperature deviation between the coolant temperature of the core and the coolant temperature of the core at the time of calculation is within ± 3 ℃, and the position deviation between the position of the inserted control rod set and the position of the inserted control rod set at the time of calculation is within ± 3.5%.
5. The method of claim 3, wherein the actual measured value of the integrated value of each of the n control rod groups is measured using a dynamic inscribe rod technique.
6. An apparatus for fitting an emergency protective value from a measured single set of wand values, comprising:
a first acquisition unit for acquiring the sum of calculated values of integral values of each of the n control rod groups
A second acquisition unit for acquiring a calculated value EP of the emergency protection value without the stickcal；
A third obtaining unit for obtaining the sum of actual measurement values of the integral value of each of the n control rod groups
A calculating unit for calculating a simulation test value according to the following formula (7)
And using the value as the measured value EP of the emergency protection valueexp：
7. The apparatus of claim 6, wherein the first obtaining unit comprises:
the first calculation program package module is used for calculating the calculation value of the integral value of each control rod group in the n control rod groups;
the first summation module is used for adding the calculated values of the integral values of the control rod groups calculated by the first calculation program package module to obtain the sum of the calculated values of the integral values of the control rod groups
Then the obtained calculated values of the integral values of all the control rod groups are summed
Sent to the calculation unit.
8. The apparatus according to claim 6, wherein the second acquisition unit comprises a second calculation package module for calculating a calculated value EP of the emergency protection value without the stick stuckcalAnd calculating the value EPcalSent to the calculation unit.
9. The apparatus of claim 6, wherein the third obtaining unit comprises:
a third measurement module for measuring an actual measurement of the integrated value of each of the n control rod groups;
a third summation module for summing the actual measurement values of the integrated value of each control rod group measured by the third measurement module to obtain the sum of the actual measurement values of the integrated value of each control rod group
Then the obtained actual measured values of the integral values of all the control rod groups are summed
Sent to the calculation unit.
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