CN105336382B

CN105336382B - Nuclear power station dynamic carves rod field conduct method

Info

Publication number: CN105336382B
Application number: CN201410404382.4A
Authority: CN
Inventors: 李志军; 郭远熊; 谭世杰; 李文; 胡汝平; 冯晓明; 徐志献; 彭松; 赵兵全; 易林; 洪志强; 张享明
Original assignee: China General Nuclear Power Corp; Daya Bay Nuclear Power Operations and Management Co Ltd
Current assignee: China General Nuclear Power Corp; Daya Bay Nuclear Power Operations and Management Co Ltd
Priority date: 2014-08-15
Filing date: 2014-08-15
Publication date: 2017-12-12
Anticipated expiration: 2034-08-15
Also published as: CN105336382A; CN107578832A; CN107578832B

Abstract

The present invention relates to nuclear power station dynamic to carve rod field conduct method, including：Three-dimensional effect amendment, the local determination for compensating electric current, quarter rod order, the optimization of zero power physics testing order and setting and inspection of advanced reactivity meter in measurement process etc..Dynamically carved in rod field conduct method obtained from improvement for the present invention, every group of control rod all independently measures, and without interference effect, rod is worth the value independent of reference bar, and measurement result reliability is high；Measurement process does not have boronation dilution operation, and the maximum reactivity that can reach depends on the reactivity of original state, safer；Measure simple to operate, mistake probability is greatly lowered；The control rod worth using position as function can be provided, there is provided the Core Design computation model required for more data verification safety analyses；Measurement efficiency is improved, overhaul critical path time is significantly saved in each overhaul at least more than ten hour；Reduce the movement of control rod and the discharge of radwaste.

Description

Nuclear power station dynamic carves rod field conduct method

Technical field

The present invention relates to nuclear plant digital control technology field, and in particular to nuclear power station dynamic is carved during rod implemented at the scene The correlation technique being related to, including three-dimensional effect amendment in measurement process, the determination of local compensation electric current, carve rod order, zero power The optimization of rate physical test order and the setting and inspection of advanced reactivity meter etc..

Background technology

Control rod is the indispensable control unit of nuclear reactor emergent control and power adjusting institute, under nominal situation, is led to Overregulate control stick position, it is possible to achieve the normal startup of reactor makes reactor be run in given power level with closing down Or carry out reactor capability regulation；Under accident conditions, reactor core reactivity is reduced by quick insertion control rod, it is tight so as to realize Jerk heap.

Control rod plays the important function of regulation reactivity in reactor, and its calculus value is very important physics Amount, therefore the value measurement of control rod calculus is the very important physical start-up experiment of one, nuclear power station.The meter of control rod worth It is more complicated at last, obtain, i.e., calculated respectively in the presence of having a control rod essentially by the CRITICAL CALCULATION of reactor With the reactivity of reactor in the presence of no control rod, the difference of the reactivity in the case of two kinds is exactly the total of required control rod Reactivity worth, abbreviation control rod integral worth.When reactor designs and runs, the different insertions of control rod are not only needed to know Value during depth, and also need to know that control rod Moving Unit at reactor core different height becomes apart from caused reactivity Change, i.e. the differential value of control rod, its unit is frequently with PCM/cm.Currently used measurement of rod worth method includes tradition Boron dilution method, rod-rod rod method (DRWM, Dynamic Rod Worth are carved to lithography and the dynamic of US Westinghouse company Measurement).Control rod calculus value can more accurately and quickly be measured by carving rod technology due to the dynamic of Westinghouse Electric And industrial quarters is enjoyed to praise highly.

Dynamically carving the General Principle of rod method is：During experiment, on the premise of boron concentration is constant during keeping testing, it is firstly introduced into About 50~70pcm positive reactivities are to improve reactor core flux level (but the flux level should be less than Doppler's heat generating spot), so Control rod group is inserted into reactor core by the way of continuous quick plunger afterwards, and the value of control rod group is continuously measured. During whole experiment, carried out using reactivity meter (ADRC, Advanced Digital Reactivity Computer) anti- Answering property calculates in real time, and records reactor core flux signal (coming from out-pile nuclear instrument RPN systems), reaction by multi-pen recorder Property instrument meter calculate reactivity, the signal such as control stick position.Dynamic carves rod method will control with normal rod speed using CRDM Rod processed inserts reactor core, can so avoid unexpected scram to the control rod impact with core structure in itself, while the duration is slightly Long, process control, is very good for test measurement and experimental data processing.

Although dynamic carves rod method measuring stick, value experiment process is fairly simple, exists when implementing at the scene and arbitrarily asks as follows Inscribe urgently to be resolved hurrily：

(1) the amendment problem of three-dimensional effect：In order that the reactivity equation derived with point reactor model, reactor core needs to locate In progressive equilibrium state.And the transient period that traditional quarter rod method needs to wait is shorter, because deviateing critical not far. Two factors work to the length of transient period, first, delayed neutron changes spatial distribution after a time delay, It causes the flux shape of delayed neutron to change with the alteration of form of prompt neutron；Second, come even for prompt neutron Say, the transition of basic mode nor change, because there are other harmonic waves while being excited, until slowly having decayed at once.It is existing There are some researches show first factor is only and plays leading role.But in critical larger reactor core change procedure is deviateed, transition Cycle is long.It is exactly so a kind of situation that dynamic, which carves rod, and during dynamic carves rod measurement, it is impossible to wait heap The transient period of core is fully completed.That is, it is necessary to be carried out to the three-dimensional effect in measurement process in dynamic carves rod measurement Theoretical correction.

(2) the determination problem of background compensation electric current：The background compensation electric current that US Westinghouse company provides determines method discomfort Background for different nuclear power station unit stations compensates electric current, causes measurement result to carve rod method with tradition and differs greatly, directly leads Control rod measurement value in part is caused mistakenly to exceed acceptance criteria.

(3) optimization problem of rod order is carved：The dynamic that US Westinghouse company provides carves rod technology and does not account for optimization quarter rod Sequentially, the characteristic of specific nuclear power station unit station is not bound with to consider the variation tendency of background compensation electric current and the shadow to rod value Result is rung, causes the dynamic to carve rod technology measurement result and is adversely affected to a certain degree by background compensation electric current, directly affected Dynamic carves the result and precision of rod.

(4) optimization problem of zero power physics testing：The dynamic quarter rod technology that US Westinghouse company provides does not account for excellent Change zero power physics testing order, be not bound with the characteristic of specific nuclear power station unit station consider moderator temperature for just and this The variation tendency of bottom compensation electric current and influence and the influence of test period to result of the test, cause the dynamic to carve the measurement of rod technology As a result adversely affected to a certain degree by background compensation electric current, directly affect the precision and result of zero power physics testing, with And the economic benefit loss that Shang Yun power plant are unnecessary.

(5) the requirement problem of reactivity meter：Dynamic carves the point reactor model usually required during rod measurement using space amendment, tool The function of standby dynamic measurement, can measure the Reactivity Measurement Facility more than 2000pcm.Require what is calculated for reactivity simultaneously Advanced reactivity meter is delivered in power range probe electric current point upper and lower part respectively, and the measuring apparatus also preferably possesses background Electric current compensation function.However, traditional reactivity meter can not possess these requirements.Therefore tool must be used when dynamic carves rod measurement The advanced reactivity meter for having dynamic to carve rod function, allows for that it is configured and checked during experiment.

The content of the invention

It is an object of the invention to carve rod by introducing, with reference to specific nuclear power station unit station feature modeling and calculating dynamic During need to carry out the Static-state Space modifying factor and dynamic space modifying factor of theoretical correction, energy during ensureing field test Enough obtain correct reactivity measurement value.On the other hand, the technical solution adopted by the present invention is：A kind of nuclear power station dynamic is provided and carves rod Three-dimensional effect modification method, it includes：The signal of the signal of upper detector and bottom detector is respectively divided by corresponding quiet The state space factor, obtains the amplitude function of upper detector and the amplitude function of bottom detector, and the Static-state Space factor is The ratio of simulation static probes signal when simulation static probes signal during plunger is extracted out with full rod；The top is visited Survey the amplitude function of device and the amplitude function of bottom detector is adjusted to identical in the value of zero moment, the top after adjustment is detected The amplitude function of device and the amplitude function of bottom detector are input in point-reactor kinetic equation after being averaged, and obtain control rod Dynamic rod is worth；The dynamic space factor amendment dynamic determined according to dynamic rod value carves the three-dimensional effect of rod, wherein The dynamic space factor is the ratio of static rod value and dynamic rod value.

Another object of the present invention, there is provided a kind of dynamic carves the background for being applied to specific nuclear power station unit station in rod field conduct Compensate the determination method of electric current.On the other hand, the technical solution adopted by the present invention is：A kind of nuclear power station dynamic is provided and carves rod field conduct The determination method of middle background compensation electric current, methods described are applied to carve with dynamic on the reactivity meter of rod pattern, the determination Method includes：Whole control rods are arranged to forbid automatically, the reactivity meter is arranged into dynamic carves rod pattern；Log-on data Record, top is mentioned by temperature adjustment rod, is determined reactivity corresponding to it, is kept the reactivity and increase flux；It is logical when increasing When amount is to preset range, with the continuous underthrust temperature adjustment rod of the maximal rate of control rod to heap bottom, separate history data file；Deng After question response heap returns to the subcritical and stable some time, perform the reactivity meter and background compensation electric current adjustment is provided itself Function.

A further object of the present invention is the variation tendency with reference to background compensation electric current and the influence result to rod value, to carry The dynamic for going out to be applied to specific nuclear power station unit station carves the quarter rod order of rod, is compensated so as to effectively reduce quarter stick value by background The influence of electric current, effectively improve dynamic and carve measurement accuracy of the rod technology in specific nuclear power station.On the other hand, the technology that the present invention uses Scheme is：A kind of nuclear power station dynamic is provided and carves the determination method that rod order is carved in rod field conduct, it includes：Compensated according to background The influence that electric current is worth with trend and background the compensation electric current of reactor core state change to rod, it is determined that dynamic carves the order of rod.

Another object of the present invention is to propose the zero power physics testing order suitable for specific nuclear power station unit station, with Just effectively reduce zero power physics testing result is influenceed by background compensation electric current, and rod measurement skill is carved so as to effectively improve dynamic Measurement accuracy of the art after the application of specific nuclear power station and the economic benefit brought to power plant.On the other hand, the skill that the present invention uses Art scheme is：The optimization method that a kind of nuclear power station dynamic carves zero power physics testing order in rod field conduct is provided, including：Adjust Whole reactor core state；Moderator temperature coefficient is measured after dynamic carves rod measurement control rod worth.

Further object of the present invention is to be established by the feature for combining specific nuclear power station unit station for dynamically carving the advanced of rod The setting of reactivity meter and inspection method, advanced reactivity meter normal work and can obtain correct during ensureing field test Reactivity measurement value.On the other hand, the technical solution adopted by the present invention is：Nuclear power station dynamic is provided and carves reactivity meter in rod field conduct Inspection method, including：Carry out functional check, high voltage control inspection, function setting, index successively to reactivity meter before starting shipment Test, adder inspection and arrangement vanning；Carry out field wiring when implementing at the scene successively to reactivity meter and examine, be average Temperature is connected with voltage-stablizer water level signal, cable connection, probe high pressure are set and background compensation electric current is set.

Brief description of the drawings

In order to illustrate the technical solution of the embodiments of the present invention more clearly, below will be in embodiment or description of the prior art The required accompanying drawing used is briefly described, and wherein same reference numerals represent same section.

Fig. 1 is carved in rod field conduct method for the nuclear power station dynamic of an embodiment of the present invention and three-dimensional effect is modified Schematic flow sheet；

Fig. 2 is the nuclear power station dynamic that the background current provided using Westinghouse Electric compensated and used an embodiment of the present invention The background current compensation electric current provided in rod field conduct method is provided and determines the site test results contrast schematic diagram that method obtains；

Fig. 3 is that the background current provided in rod field conduct method is carved using the nuclear power station dynamic of an embodiment of the present invention Compensation electric current determines that method carries out the schematic diagram of the revised site test results of background current；

Fig. 4 is that typical background compensates trend schematic diagram of the electric current with reactor core state change in a nuclear power station；

Fig. 5 is the arrangement schematic diagram of control rod wherein in the specific reactor core of a nuclear power station；

Fig. 6 is carved in rod field conduct method for the nuclear power station dynamic of an embodiment of the present invention and optimized to carving rod order Schematic flow sheet；

Fig. 7 carves suitable to zero power physics testing in rod field conduct method for the nuclear power station dynamic of an embodiment of the present invention The process schematic that sequence optimizes.

Embodiment

Dynamic of the present invention based on US Westinghouse company carves rod method, it is proposed that nuclear power station dynamic carves rod field conduct side Method, this method are related to three-dimensional effect amendment in measurement process, the determination of local compensation electric current, carve rod order, zero energy physics The optimization of test sequence and the setting of advanced reactivity meter and inspection etc..

The present invention is described in further detail below by embodiment combination accompanying drawing.

[embodiment 1]

The present embodiment provides a kind of nuclear power station dynamic and carves the method being modified in rod field conduct method to three-dimensional effect, It can be obtained correctly by introducing the Static-state Space factor and the dynamic space factor with ensureing that dynamic is carved when rod method is tested at the scene Reactivity measurement value.

The Static-state Space factor is actually normalized spatially distributed functions, usually, the Static-state Space factor=plunger When simulation static probes signal/full rod extract the simulation static probes signal of (ARO, All Rods Out) out.

The rod that rod value corresponding to the reactivity obtained by the Static-state Space factor is tried to achieve with conventional method is worth and endless Full equity, because in the measurement process that dynamic carves rod, the spatial distribution of delayed neutron does not have enough time also reaching progressive Equilibrium state.Here the rod value that dynamic quarter rod is tried to achieve by the Static-state Space factor and reactivity equation referred to as (is calculated into) dynamic Rod is worth, and the reactivity that conventional method (can also be called static method) is obtained referred to as (calculates) static rod value.Conventional method is Including traditional measurement of rod worth method such as periodic method, rod drop method.

It is worth to obtain consistent with static rod value, can be directly compared with static theory calculated value a rod, Here the dynamic space factor is introduced；Obviously, static rod value/(calculating) dynamic rod value of the dynamic space factor=(calculating).

The present embodiment nuclear power station dynamic carve rod three-dimensional effect modification method, even if actually introduce Static-state Space because The application of son and the dynamic space factor, as shown in figure 1, comprising the following steps：

Step S101, i.e., by the signal of the signal of upper detector and bottom detector difference divided by corresponding Static-state Space The factor, obtain the amplitude function of upper detector and the amplitude function of bottom detector；

Step S103, i.e., it is magnitude function is identical in the value adjustment of zero moment, detector sensitivity difference is got rid of, so It is input to after the two magnitude functions are averaged afterwards in point-reactor kinetic equation, obtains the dynamic rod value of control rod；

Step S105, the Static-state Space factor being calculated according to dynamic rod value and conventional method, determines dynamic Steric factor.

According to the dynamic space factor determined, final control rod worth is：Final control rod worth=dynamic space The factor × dynamic rod value.

In a kind of specific example, the calculating that the dynamic of the present embodiment carves the space modifying factor of rod method can be based on U.S. west The pressurized water reactor core Embeded Software bag APA8 Development of Software Package of room company exploitation obtains.APA (ALPHA/PHOENIX-P/ANC) journey Sequence system is to have obtained the certification of U.S.'s core pipe meeting, is widely used in the U.S., Europe and all over the world pressurized-water reactor nuclear power plant Nuclear design, there is substantial amounts of engineer applied experience.APA programming systems mainly include PHOENIX-P, ALPHA and ANC tri- Individual main-line program, the auxiliary program incidentally calculated comprising some other additional functions and execution support program, wherein PHOENIX-P and ANC is that bidimensional transport theory component fuel power spectrum program and Nodal method of deploying reactor core calculate journey respectively Sequence.ALPHA is the bridge of the two programs of PHOENIX-P and ANC, is automatic connection PHOENIX-P and ANC interface routine. Here these three programs are somewhat introduced.PHOENIX-P is the fuel assembly power spectrum calculation procedure of a bidimensional multigroup transport theory, To provide the homogenization nuclear cross section parameter of fuel assembly.PHOENIX-P programs use 70 based on ENDF/B-VI The basic nuclear cross section storehouse of group, PHOENIX-P carry out the solution of space-Energy distribution of neutron flux using two steps, and the first step is Method based on collision probability and response matrix, 70 groups of locking nub solutions of two dimension of fuel assembly are tried to achieve, it is by each lattice cell sub-district (core Block, involucrum, moderator) be coupled with the lattice cell around it, thus maintain lattice cell and around it lattice cell heterogeneity. Locking nub solution gives accurately and the distribution of detailed local netron-flux density, the distribution of these netron-flux densities will be used for lattice cell Homogenization.Second step is that the lattice cell tried to achieve using the first step homogenizes data, and fuel stack is carried out with the discrete ordinates method of standard Part is calculated to determine few group of group constants of fuel assembly.PHOENIX-P programs have the fuel assembly for simulating various presurized water reactors The ability of type and burnable poison type.ANC programs are built upon the advanced locking nub program on the basis of Nodal method of deploying. ANC programs can be used for predicting reactivity, power distribution and burnup profile of reactor core under various operating modes etc..ANC programs are adopted Nodal method is made up of following three parts：Nonlinear nodal expansion method, rod power are rebuild, equivalent homogenization is theoretical.In addition The enthalpy that ANC programs also carry out reactor core rises calculating, xenon effect calculates and Doppler feeds back calculating etc.；And realizing fuel assembly Burnup calculate, reactivity coefficient calculate, control rod worth calculate etc. there is very high automaticity.ALPHA programs It is an automatic connection fuel assembly power spectrum calculation procedure PHOENIX-P and reactor core calculation procedure ANC user interface program.It Can provide it is effective, meet method actual, that PHOENIX-P procedural models are set and transmit cross-section data for ANC programs. User provides basic parameter for ALPHA programs, including：Geological information, material information, the hot-working hydraulic characteristic letter of reactor core Breath and fuel assembly composition information etc., then, ALPHA programs can automatically generate the input card and calling of PHOENIX-P programs PHOENIX-P programs carry out fuel assembly power spectrum calculating, while interface data is imported in ANC input card.In addition, user is also The input card of the PHOENIX-P as caused by ALPHA programs can be voluntarily changed, to realize more flexible calculating.

For the specific example, because the flow that DRWM amendment steric factors calculate is complex, and according to intermediate computations As a result need rule of thumb to carry out appropriate adjustment, only list the committed step of whole calculation process herein, including it is as follows：

Step S1001：Input card prepares.That is, ALPHA input cards (such as alphai.inp, alphai_ are generated using ALAMO Ag.inp, alphai_ss.inp) and ANC input cards (such as anci.inp).

Step S1002：ALPHA is calculated.That is, ALPHA job files are performed, call PHOENIX-P Program Generating components Cross-section library.ALPHA obtains accurate boron by iteration and drops curve.First time iteration uses initial boron to drop curve, is tied with it Fruit (section, pin and pinmap files) input ANC calculates new boron drop curve.Inputted again with newly-generated boron drop curve ALPHA calculates the final theoretical model that new more accurate cross section information is used to generate ANC.

Step S1003：Control rod section modifying factor calculates.That is, beginning of life (BOL, Beginning of Life), Control rod insertion shape is generated under longevity interim (MOL, Middle of Life), the end of term in longevity (EOL, End of Life) burnup respectively Cross-section data under state.Here the phase in longevity is core life, refers to that reactor core is able to maintain that the time of effective Operation at full power, Generally in PWR nuclear power plant, according to the length of reactor core run time, core life is divided into BOL, MOL and EOL.

Step S1004：ANC is calculated.That is, 3D core models are obtained by ANC.

Step S1005：ANC result verifications (Benchmark performance tests).That is, with the ANC 3D generated during calculating Model can be controlled the calculating of rod value, isothermal temperature coefficient etc., by obtained parameter and actual measured results or The result that SCIENCE is calculated is compared, and the validity of model can be verified, so as to ensure that final step is calculated correctly DRWM spaces modifying factor.

Usually, it is (referring both to absolute value below) with reference to acceptance criteria：ARO critical boron concentration deviations<50ppm；It is theoretical-real Survey isothermal temperature coefficient deviation<5.4pcm/C；Theoretical isothermal temperature coefficient deviation<3.6pcm/C；Moderator temperature coefficient deviation< 3.6pcm/C；Rod value departure<10%.

Empirical tests, above parameter all meet the calculating that could carry out space modifying factor after requirement on this basis.If There is the situation beyond acceptance criteria, it is necessary to provide reasonable dismissal confirm can model of endorsement validity.

Step S1006：DRWM spaces modifying factor calculates.That is, by PHIRE Program Generating neutronics constant (during wink is sent out Sub- life-span, delayed neutron fraction and decay coefficient).

Space modifying factor is calculated using ANC.Ultimately generate the space modifying factor Ziwen of the 9 groups of rods used in ADRC Part (such as bank_g1.dsn~bank_sd.dsn).

In another specific example, newly feed in reactor or newly reload, it is corresponding empty before measurement of rod worth Between the work of effect corrected Calculation completed, i.e., in the reactor design phase, heap core is established with corresponding reactor core software for calculation Type, the rod group process of falling during actual reactor core physical test stage control rod value measurement is simulated, obtains each control rod group along axle To the Static-state Space factor and the dynamic space factor corrected point by point, then reactivity meter is input to using calculated value as parameter The change of reactivity (tracking), so as in the physical test stage of reality, can use the Static-state Space factor and dynamic space because Son obtains final revised control rod worth according to aforementioned method steps.

The present embodiment obtains the Static-state Space factor for being used for correcting dynamic quarter rod three-dimensional effect by introducing, modeling and calculate It is accurately reactive to be obtained in rod measurement process is dynamically carved so that security and economy are obvious with the dynamic space factor The dynamic that rod is carved higher than tradition carves the introducing of rod technology (such as DRWM of Westinghouse Electric's offer) and applied to specific nuclear power station It is possibly realized.

[embodiment 2]

The present embodiment provides a kind of nuclear power station dynamic and carves the method that background compensation electric current is determined in rod field conduct method, its The ADRC with DRWM patterns based on US Westinghouse company's exploitation is realized, comprises the following steps S201~S206.

Step S201：Confirm that control rod is all placed in manually (to forbid automatic), and the maximum translational speed of whole control rods It has been set that, for example, 72 steps/point.Control rod group is divided into three classes, i.e., power back-off rod group (G rods and N rods, including as G1, G2, N1, N2), temperature adjustment rod group (R rods) and shut-down rod group (S rods, including such as SA, SB, SC and SD).

Step S202：ADRC is arranged to DRWM patterns, the range for adjusting multi-pen recorder is set.

Step S203：Rod motion is carved in dynamic to start (boronation uniformly after) and terminate each major loop of Manual analysis and surely The boron concentration of depressor is simultaneously recorded, it is desirable to and the absolute value of boron concentration difference is less than preset range between major loop and voltage-stablizer, Such as 20ppm.

Step S204：Confirm that data record (Filing) has been started up, carry R rods to top, confirm reactivity in predetermined model Enclose for example near 60pcm, keep the reactivity, increase flux.

Step S205：When flux rises to preset range, (such as about the 75% of the upper limit, this value obtains according to actual conditions Arrive, such as in view of real time feedback influence etc.) when, start with the continuous underthrust temperature-compensating rod of maximal rate (i.e. R rods) extremely The step of heap bottom 5, first stop (Stop) and restart (Start) data record (Filing) to separate history data file.

Step S206：Wait reactor to return to subcritical, after for example, at least half an hour stable some time, adjust ADRC sheets Bottom compensates electric current, i.e. Main Menu-CALIBRATION FUNCTION-Leakage Current Determination/ Compensation–Automatically Adjust Leakage Currents。

Such as DRWM patterns that are related in above-mentioned steps, Stop, Start, Filing, Main Menu etc. are existing The function or menu provided in the ADRC with DRWM patterns for the exploitation that US Westinghouse company provides.

Background compensation electric current in the ADRC provided at present using US Westinghouse company determines method, and it obtains heat and stops full rod This earth-current that insertion (ARI, All Rods In) state is set causes rod value measurement result deviation larger, sees Fig. 2.And adopt With the above-mentioned determination method of the present embodiment before off-test, the state that other rods put forward entirely is inserted in R rod G2 rods during field conduct Under, reset and background current, and the measurement of R rods and SD rods has been re-started, as a result it is obviously improved, still as shown in Figure 2.Figure It is that the dynamic control rod value measurement after background compensation electric current is determined using the present embodiment corresponding to DRWM in shown in 2 The result of (Dynamic Rod Worth Measurement), it is to use traditional dilution method and alternating corresponding to conventional method Method measures the result of control rod worth, is the theoretical calculation obtained using existing seed nucleus design count software corresponding to SCI As a result, it is that (for example DRWM measurement results are D to deviation of the DRWM and SCI theoretical values in measurement result, SCI reasons corresponding to e_DS Be s by result of calculation, then e_DS=(D-S)/S*100%), be corresponding to e_DT e_DS similar with e_DA implication, i.e. e_DT The deviation of DRWM and conventional method in measurement result, it is that DRWM and APA theoretical values are inclined in measurement result corresponding to e_DA Difference.

Based on experiment flux (i.e. PRC electric currents) response it is constant, by correct background current to experiment flux influence (such as Correct bank_XX.dat and bank_XX.ic files middle and upper part flux and bottom flux), using ADRC off-line calculation functions, obtain It is as shown in Figure 3 to new result of the test.In shown in Fig. 3, compensated using the present embodiment revised version bottom corresponding to the method for amendment The dynamic obtained after electric current carves rod measurement result, is using traditional dilution method and alternative method measurement control corresponding to conventional method The measurement result of rod value, is the calculated results obtained using existing seed nucleus design count software corresponding to SCI, e_ It is that rod measurement result (also known as DRWM results) is carved using the dynamic obtained after the present embodiment revised version bottom compensation electric current corresponding to CS And SCI theoretical values deviation (for example DRWM measurement results are D, SCI the calculated results are s, then e_DS=(D-S)/S* 100%), e_DT e_DSs similar with e_DA implication, i.e. be DRWM results corresponding to e_CT with conventional method in measurement result Deviation, be the deviation of DRWM results and APA theoretical values in measurement result corresponding to e_CA.

From figure 3, it can be seen that result of the test and the fine (relative deviation of traditional measurement result accordance after background current amendment e_CT<3.0%).

To sum up, the background compensation electric current that the method that the present embodiment provides efficiently solves US Westinghouse company's offer does not apply to In other nuclear power station unit stations the defects of, cause dynamic to carve the normal measurement result of deviation of rod measurement value mistake, rod is carved for dynamic The final success of technology is introduced and is incorporated in other nuclear power stations and cleared away one of significant obstacle.

[embodiment 3]

In order to explore the influence that background current setting is worth measurement result to rod, tested using different background current amendments logical Amount carries out sensitivity analysis.Fig. 4 diagrammatically illustrates certain nuclear power station background compensation electric current in overhaul and become with reactor core state change Gesture, wherein " being diluted to about CBcri+125ppm " and referring to the theoretical high 125ppm of boron concentration, " after R1 values are bigger than normal, Rin " refers to that R is controlled Rod group processed is inserted into the step of reactor core 5 extraction step and put, and " R+G2in " refers to that R and G2 control rod groups are inserted into reactor The step of core 5 is extracted step out and put.It can be seen that stopping, under ARI states (non-standard heat is stopped) in unit heat, PRC backgrounds are measured, are found：Just set When complete background compensation electric current, the reading of top and the bottom PA (planar detector, plane array) table is micro- just (micro- just or micro- It is negative to refer to that measured current is bigger than normal compared with background compensation current or magnitude less than normal is about below 10^-10A), but up to after critical, should Reading is micro- negative；Therefore it is excessive to judge that compensation electric current is set.Find that control rod worth is generally bigger than normal after measurement, this is due to compensation Electric current sets excessive cause.

Analysis result shows：It is more sensitive that 1. rod is worth big control rod pair background current setting；2. background current is arranged on At 0.85~1.05 times of reasonable level, result error is can be controlled within 10%；3. background current sets then measurement knot less than normal Fruit is small, sets then measurement result bigger than normal big, and sets bigger than normal than setting the influence less than normal to result bigger；4. close to the control of probe Rod processed sets more sensitive to background current.

The DRWM technologies that US Westinghouse company provides at present do not account for optimization and carve rod order, do not consider specific nuclear power yet Stand the characteristic of unit, understand that use is this with reference to the variation tendency of above-mentioned background compensation electric current and to the influence result that rod is worth The DRWM technologies for carving rod order of specific nuclear power station unit station are not accounted for, its measurement result can be compensated electricity by background to a certain degree The adverse effect of stream, directly affect result and precision that dynamic carves rod.

Therefore, the variation tendency with reference to background compensation electric current and the influence result (i.e. foregoing 1.~4.) that is worth to rod, Embodiment proposes to carve the quarter rod order of rod suitable for the dynamic of specific nuclear power station unit station, to reduce background compensation current drift pair Being worth the measurement of big rod influences.By taking the arrangement of control rod shown in Fig. 5 as an example, then dynamic quarter rod order is：R→N1→SD→SB →G2→SC→SA→N2→G1。

In a kind of specific example, dynamic carves rod order, and constant current journey comprises the following steps S3001~S3009 really, such as Fig. 6 institutes Show.

Step S3001：Measure R rods value.

In this step, R rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；So R rods are above carried afterwards to heap top, and keep the reactivity, increase flux；Start the set point of collection (as led to when flux rises to data Measure the upper limit 50%), prepare underthrust R rods；When increment is risen near 75% for setting and reaching the standard grade, start continuous with maximal rate Underthrust R rods are to heap bottom；When ADRC reactivity meters require that user inputs control rod information, start above to carry R rods to top, while root According to ADRC prompting, input R rods title, start rod position and terminate the information such as rod position, so as to obtain R rods value.The step for In, if use provides rod action signal manually or rod action signal is unavailable, using manual while underthrust is started Mode gives ADRC reactivity meter rod action signals, under be inserted into behind heap bottom and remove rod action signal manually；And during upper carry, Operator needs to pay close attention to range doubling time table among master control two, if the instruction of doubling time ID table is close to 30s or goes out Existing RPN419AA alarms, can suitably stop rod withdrawal, but in the case where the doubling time allows, to propose R rods, Yi Miandui as early as possible Core flux is down to too low.

Step S3002：Measure N1 rods value.

In this step, N1 rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust N1 rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust N1 rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry N1 rods to top, while according to ADRC prompting, input N1 rods title, start rod position and Terminate the information such as rod position, so as to obtain N1 rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose N1 rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3003：Measure SD rods value.

In this step, SD rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust SD rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust SD rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry SD rods to top, while according to ADRC prompting, input SD rods title, start rod position and Terminate the information such as rod position, so as to obtain SD rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose SD rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3004：Measure SB rods value.

In this step, SB rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust SB rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust SB rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry SB rods to top, while according to ADRC prompting, input SB rods title, start rod position and Terminate the information such as rod position, so as to obtain SB rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose SB rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3005：Measure G2 rods value.

In this step, G2 rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust G2 rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust G2 rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry G2 rods to top, while according to ADRC prompting, input G2 rods title, start rod position and Terminate the information such as rod position, so as to obtain G2 rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose G2 rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3006：Measure SC rods value.

In this step, SC rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust SC rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust SC rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry SC rods to top, while according to ADRC prompting, input SC rods title, start rod position and Terminate the information such as rod position, so as to obtain SC rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose SC rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3007：Measure SA rods value.

In this step, SA rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust SA rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust SA rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry SA rods to top, while according to ADRC prompting, input SA rods title, start rod position and Terminate the information such as rod position, so as to obtain SA rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose SA rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3008：Measure N2 rods value.

In this step, N2 rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust N2 rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust N2 rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry N2 rods to top, while according to ADRC prompting, input N2 rods title, start rod position and Terminate the information such as rod position, so as to obtain N2 rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose N2 rods as early as possible, so as not to reactor core flux be down to it is too low.

Step S3008：Measure G1 rods value.

In this step, G1 rods are selected using rod position selecting switch, and confirms that data record (Filing) has been started up；When Flux rises to the set point (such as the 50% of the flux upper limit) that data start collection, prepares underthrust G1 rods；Set when increment rises to When near 75% to reach the standard grade surely, start with the continuous underthrust G1 rods of maximal rate to heap bottom；When ADRC reactivity meters require that user is defeated When entering control rod information, start above to carry G1 rods to top, while according to ADRC prompting, input G1 rods title, start rod position and Terminate the information such as rod position, so as to obtain G1 rods value.In this step, rod action signal or rod are provided manually if used Action signal is unavailable, then gives ADRC reactivity meter rod action signals, underthrust using manual mode while underthrust is started Rod action signal is removed after to heap bottom manually；And during upper carry, operator needs to pay close attention to range among master control two Doubling time table, if the instruction of doubling time ID table is close to 30s or RPN419AA alarms occurs, it can suitably stop rod withdrawal, but The doubling time allow in the case of, to propose G1 rods as early as possible, so as not to reactor core flux be down to it is too low.

The variation tendency and the influence result to rod value of the present embodiment combination background compensation electric current, it is proposed that suitable for tool The dynamic of body nuclear power station carves the quarter rod order of rod, and effectively reduce to carve rod and be worth is influenceed by background compensation electric current, is effectively improved Dynamic carves the measurement accuracy of rod e measurement technology.

[embodiment 4]

The definition of moderator temperature coefficient is that reactor core moderator mean temperature often changes reactive change caused at 1 DEG C Change.Change and control of the moderator temperature coefficient to reactor core reactivity are extremely important, and being reactor in core design, itself is intrinsic Self-stability quality important indicator and ensure reactor safety operation an important parameter, in nuclear power station running technology specification Middle clear stipulaties, never allow under any operating condition moderator temperature coefficient occur on the occasion of.Therefore, moderator temperature coefficient First time measurement result is timing, it is necessary to carry out the measurement of second of moderator temperature coefficient.

The zero power physics testing order that US Westinghouse company suggests at present is that dynamic quarter rod measurement is placed in into dynamic to carve rod Afterwards, then need to readjust reactor core state to meet that dynamic is carved needed for rod after second of moderator temperature coefficient measurement terminates Initial reactivity requirement, this will cause the increase of test period.

Variation tendency with reference to foregoing background compensation electric current and the influence result to rod value, and consider moderator temperature Coefficient is that timing needs to carry out the measurement of second of moderator temperature coefficient, and the present embodiment provides a kind of nuclear power station dynamic quarter rod and showed The optimization method of zero power physics testing order during field is implemented.After moderator temperature coefficient is placed in dynamic quarter rod by this method, If necessary to carry out second of moderator temperature coefficient measurement, the reactor core state after measurement terminates carves rod without the concern for dynamic Initial reactivity requirement, it is only necessary to consider that zero power physics testing terminates the requirement of rear reactor core, now second of moderator temperature Reactor core state after degree coefficient measurement terminates can directly meet the requirement that zero power physics testing terminates；Thus can reduce The adjustment time of reactor core state.

A kind of implement shows that the nuclear power station dynamic of the present embodiment is carved in rod field conduct method to zero energy physics The general procedure for the method that test sequence optimizes, comprise the following steps S401~S406, as shown in Figure 7.

Step S401：Reactor core state adjusts.

, it is necessary to complete source range protection definite value adjustment before performing the step and being adjusted state, and RGL is provided with (nuclear power plant's control rod mobile control system) control rod maximum translational speed, for example, 72 steps/minute, ADRC reactivity meters still make With RHO (a kind of measurement pattern in Advanced Reactivity Measuring Facility) pattern.

In this step, adjust reactor state to reactivity during ARO in 50pcm between 75pcm.

R rods are proposed during appropriate boronation if necessary to meet above-mentioned condition.R rods are used during boronation so that reacting Heap is in stable condition.

It can also record or calculate R rods initial position, R simultaneously_iBoron concentration, R rods under rod position are from R_iValue to ARO, Boron differential worth, the boron concentration that need to change, R rods are in target rod position R under the high boron water boron concentration of REA, current boron concentration_tWhen estimated boron Concentration value, boron amount, boronation speed need to be added.Then boronation operation is carried out.During boronation waits uniformly after terminating, adjustment flux is to about 15% (numerical value is determined on a case-by-case basis, and is merely illustrative of here), R rods are manually mentioned into top, judged uniform Whether reactor core state can meet requirement (be greater than 50pcm and be less than 75pcm) afterwards, if meeting, then adjust underthrust R rods logical Critical rod position is placed in after amount to preset range (such as less than 50%), can not such as be met, then continues regulation until meeting to require. Then R rod critical rods position after boronation, record ARO states reactor core reactivity and actual plus boron amount are recorded.

Step S402：Measure control rod worth.

Before this step is performed, preparation is measured first, including：Perform the background compensation electric current addressed in embodiment 2 Determination method, after reactor core Critical Stability, using the optimization addressed in embodiment 3 quarter rod order, by the optimization order enter Mobile state carves rod.Specifically, comprise the following steps：

Step S4021：Confirm that control rod is all placed in manually (to forbid automatic), and the maximum translational speed of whole control rods It has been set that, for example, 72 steps/point；

Step S4022：ADRC is arranged to DRWM patterns, the range for adjusting multi-pen recorder is set, also, is carved in dynamic Rod motion starts (boronation is uniformly rear) and the boron concentration for terminating each major loop of Manual analysis and voltage-stablizer and recorded, The absolute value of boron concentration difference between major loop and voltage-stablizer is asked to be less than preset range, such as 20ppm；

Step S4023：Confirm that data record (Filing) has been started up, carry R rods to top, confirm reactivity in predetermined model Enclose for example near 60pcm, keep the reactivity, increase flux；

Step S4024：When flux rises to preset range, (such as about the 75% of the upper limit, this value obtains according to actual conditions Arrive, such as in view of real time feedback influence etc.) when, start with the continuous underthrust temperature-compensating rod of maximal rate (i.e. R rods) extremely The step of heap bottom 5, first stop (Stop) and restart (Start) data record (Filing) to separate history data file；

Step S4025：Wait reactor to return to subcritical, after for example, at least half an hour stable some time, adjust ADRC Background compensates electric current, i.e. Main Menu-CALIBRATION FUNCTION-Leakage Current Determination/ Compensation–Automatically Adjust Leakage Currents；

Step S4026：R rod recovery of criticals are above carried, timely locking source range after " P6 " appearance is paid attention to, avoids trigger source range Heap is jumped in protection；

Step S4027：The horizontal change of passing flux judges whether that up to critical, after reactor core Critical Stability, preparation starts to measure The value of each group control rod.

Such as DRWM patterns that are related in above-mentioned steps S4021~S4027, Stop, Start, Filing, Main Menu Etc. be the exploitation that existing US Westinghouse company provides the ADRC with DRWM patterns in the function that provides or menu.

After completing measurement and preparing, using the foregoing optimization method for carving rod order, to reduce background compensation current drift The measurement for being worth big rod is influenceed.In a kind of specific example, dynamic carves rod order, and constant current journey comprises the following steps S402a really ~S402i.

Step S402a：Measure R rods value.

Step S402b：Measure N1 rods value.

Step S402c：Measure SD rods value.

Step S402d：Measure SB rods value.

Step S402e：Measure G2 rods value.

Step S402f：Measure SC rods value.

Step S402g：Measure SA rods value.

Step S402h：Measure N2 rods value.

Step S402i：Measure G1 rods value.

After completing all measurement of rod worth, underthrust R rods, reactor flux is controlled and made a reservation in predetermined ADRC flux Scope, such as 15%~20% (i.e. near the 50% of the zero power physics testing upper limit), the valency of all control rods can also be recorded It is worth and compares theory value deviation, it is folded moved further pattern then to recover power rod group, recovers the mobile speed of maximum of RGL control rods Degree.

Step S403：Measure ARO critical boron concentrations.

Critical boron concentration calculate after ADRC exits DRWM patterns, into carrying out before RHO patterns.Need during this period Pay attention to keeping reactor core in stable condition.

In this step, question response heap is stable after critical condition, exits ADRC DRWM patterns.In ADRC main menus In, critical boron concentration analysis (i.e. ANALYZE-DRWM Boron Endpoint Calculation) is performed, is selected all DRWM.IC files (reactivity and temperature information that include ARO states), and input dynamic and carve rod device Manual analysis boron concentration Average value (see abovementioned steps S4022).Record the critical boron concentration result of ADRC reactivity meters measurement.

Step S404：Measure ARO isothermal temperature coefficients.

In order to keep the inconvenience of the boron concentration of reactor coolant loop during testing, unit need to meet following requirements： RCV002BA unit water levels highest (as being 1.7m) and stable some time (such as half an hour, and before cooling)； RCV002BA is in " STOP " position (supply water selector)；One lower discharging hole plate input；Mixed bed demineralization device is isolated；Voltage-stablizer Back-up heater input；APG (Steam Generator Blowdown, steam generator blowdown system) blowdown flow reduces Such as it is reduced to below 30t/h；RCP if (reactor coolant loop, Reactor Coolant System) boron density unevenness Even (such as difference>10ppm), with " manual " control voltage-stablizer water level, voltage-stablizer water level otherwise is controlled with " automatic ", if with manually The water level of voltage-stablizer is controlled, maintains constant water level or slightly elevated water level.

In this step, in an initial condition, it is according to the requirement of cooling (or heating), and the temperature coefficient estimated in advance Just (or negative), flux level regulation is arrived by mobile R rods group by defined scope, and maintenance reaction heap Critical Stability.Pass through tune Save GCT (Turbine Bypass, Steam Turbine Bypass System) to discharge to air, complete from starting mean temperature cooling is warming up to again The operation of beginning temperature (about 2 DEG C heat up about 2 DEG C again such as cooling), it is desirable to which rate of temperature change is such as 4 DEG C/h or so, and record related ginseng Number.When starting cooling/heating, in ADRC reactivity meter RHO mode menus, isothermal temperature coefficient analysis is performed (i.e. Options–ANALYZE-ITC-Start).Stop analysis (i.e. Options-ANALYZE-ITC- at the end of cooling/heating Stop).Certainly, the water level that RCV002BA appearance control casees should be looked over one's shoulder during experiment is no more than predetermined value (such as 2.01m), because For usually, 1.95m is highest liquid level warning signal, and 1.10m is minimum liquid level alarm signal, and is then closed during 0.85m RCV033VP and RCV034VP.To ADRC cool and heat up measurement result weighted average twice, obtain isothermal temperature coefficient Measurement result.Measurement result should meet to require as follows, that is, cools and the difference of measurement result twice that heats up is less than 2pcm/ DEG C, and And the absolute value of the difference between measured value and the calculated value that is calculated using commonsense method is less than or equal to 5.4pcm/ DEG C.This Also check for whether measurement result meets safety criterion outside, i.e. moderator temperature coefficient is negative.

Step S405：Determine moderator temperature coefficient for negative boron concentration limit.

The step is optional step, and it carries out the isothermal temperature coefficient measurement under estimated boron concentration ± 25ppm.Target boron is dense Spend and can guarantee that moderator temperature coefficient is negative boron concentration limit for estimated.Detailed process can be：Reactor Critical Stability In zero load test scope, R rods are at regulation band middle part (more than the step of lower bound 197)；Dilute water；Dilution rate；By It can be compensated in reactive flux caused by dilution by constantly inserting the complete step number of GG rod groups.Preferably, reactivity meter Changes of reactivity control between ± 40pcm, flux level is maintained near 50%.When boron concentration reach estimated boron concentration+ Stop dilution during 5ppm, continue the uniform effect after being diluted with the compensation of GG rods, while record actual dilution water.In original state Under, according to the requirement of cooling (or heating), and the temperature coefficient estimated in advance is just (or negative), by mobile R rod groups flux Level tune scope as defined in, and maintenance reaction heap Critical Stability.By adjusting GCT (Turbine Bypass, turbine by pass System) to be discharged to air, the operation for completing to be warming up to initial temperature again from starting mean temperature cooling (rises again as cooled about 2 DEG C About 2 DEG C of temperature), it is desirable to rate of temperature change is such as 4 DEG C/h or so, and record relevant parameter.It is anti-in ADRC when starting cooling/heating In Ying Xingyi RHO mode menus, isothermal temperature coefficient analysis (i.e. Options-ANALYZE-ITC-Start) is performed.Cooling/liter Stop analysis (i.e. Options-ANALYZE-ITC-Stop) at the end of temperature.Certainly, should be looked over one's shoulder during experiment The water level that RCV002BA holds control case is no more than predetermined value (such as 2.01m), because usually, 1.95m is highest liquid level warning signal, 1.10m is minimum liquid level alarm signal, and RCV033VP and RCV034VP are then closed during 0.85m.ADRC is being cooled and heated up Measurement result weighted average twice, obtain isothermal temperature coefficient measurement result.Measurement result should meet to require as follows, that is, cool It is less than 2pcm/ DEG C with the difference of measurement result twice of heating, and measured value is with using the calculated value that commonsense method is calculated Between difference absolute value be less than or equal to 5.4pcm/ DEG C.Additionally whether check measurement result meets safety criterion, i.e. slowing down Agent temperature coefficient is negative.By the isothermal temperature coefficient that measures under this measurement and ARO states and critical boron concentration at that time, with interior Insert or the method for extrapolation determines to ensure moderator temperature coefficient as negative highest boron concentration, and can also be in the form of TOI to operation Place proposes run-limiting.

Step S406：Recover set state.

In this step, confirm and adjust following equipment to rational state：Except salt bed, on-off type heater, letdown flow Orifice plate.

Unit is adjusted to following state：Safety rod (including SA, SB, SC, SD) carries (as being 225 steps) entirely, by power back-off Rod group is carried to more than zero energy scale rod position (for the value set in unit), temperature control rod R rods be lower bound more than (and to the greatest extent May be in regulation band), boron concentration is that can ensure that moderator temperature coefficient is negative value, and primary Ioops mean temperature is preset range Interior such as 290.4 DEG C -293.4 DEG C.

The present embodiment combination moderator temperature coefficient is that timing needs to carry out second moderator temperature coefficient measurement, background Compensate the variation tendency of electric current and the influence result to rod value, it is proposed that suitable for the zero energy physics of specific nuclear power station unit station Test sequence, influenceed so as to effectively reduce zero power physics testing result by background compensation electric current, and compared with Westinghouse Electric The zero power physics testing order of offer is effectively shortened the test period that moderator temperature coefficient is timing, effectively increases The economic benefit that dynamic is carved the measurement accuracy of rod e measurement technology and brought to power plant.

[embodiment 5]

Dynamic must use the point reactor model of space amendment when carving rod measurement, possess the function of dynamic measurement, can measure Reactivity Measurement Facility more than 2000pcm.Simultaneously require for reactivity calculate power range pop one's head in electric current, divide top and Advanced reactivity meter is delivered in bottom respectively.The measuring apparatus must also possess background current compensation function.Traditional reactivity meter Can not possess requirements above.There is dynamic on the other hand, present embodiments providing and must be used when a kind of nuclear power station dynamic carves rod measurement The advanced reactivity meter of rod function is carved, it allows for being set and checking during experiment.A kind of example is based on U.S. west The ADRC with DRWM patterns of room company exploitation realizes the setting and inspection to ADRC.

A kind of implement shows that the nuclear power station dynamic of the present embodiment is carved in rod field conduct method to advanced reactivity The general procedure of setting and the inspection of instrument, it is specific as follows：

Step S501：Prepare (including determining correlated condition and regulation) and initial setting up in advance.

Here condition includes：Prerequisite, associated documents and equipment.

Prerequisite includes as follows：The formal report of refueling design side's offer is provided, and started according to report generation Physical test Parameter File (adrc.ndr and bank_XX.dsn)；Instrument and meter has been examined and determine on schedule；This program operational staff is ripe Know windows operating systems and the structure of ADRC hardware and softwares；Before connecting PRC cables, unit is in standard hot shutdown condition, And when connecting, power plant's instrument control departmental staff's on-site support.

Associated documents are included for example《ADRC User’s Manual》, test cycle《Startup physics test is reported》And examination Test circulation《Dynamic carves rod factor file》.

Equipment includes：Special-purpose USB flash disk；Test the ADRC sequence codes used；During expected experiment, high-voltage power supply is (as that need to make By the use of) and must be in the calibration certificate term of validity as the top current source of internal calibrating benchmark；During expected experiment, it is in Examine and determine the Fluke715 or other voltage sources in the term of validity, it is desirable to 0~10V voltage outputs function and 0~10V voltage measurement functions Assay approval；During the experiment prefetched, the universal meter in the calibrating term of validity.

Regulation includes following risk：Inappropriate operation may damage or consume instrument and meter, cause unnecessary economy Loss；Incorrect setting may influence monitoring of the personnel to reactor in Startup physics test；Using palpus during high-voltage power supply especially Pay attention to, prevention high-voltage electric shock is caused injury；When instrument is carried and furnished, pre- overturning-preventing extruding and sharp corner are hurted sb.'s feelings.Also, performing In subsequent step, if any any exception, instrument test engineer processing is contacted if necessary.In case of exceptional circumstances, in instrument test Under engineer instructs, the order that can not press subordinate's step performs ADRC inspections and set.

One kind is in the specific implementation, initial setting up includes following content：

ADRC case lids are opened, check I/O panels " TOP ", " BOTTOM " and " three UHF butts cleanings of HIGH VOLTAGE " Degree, is cleaned if needed；

Correct connection each parts of ADRC, including power line, PC signal transmssion lines, IEEE data/address bus, SLC signal transmssion lines Deng；

All appts are opened, each part instrument sequence code and operational mode (referring to ADRC user's manuals) is confirmed, confirms to seek Location address sets (referring to ADRC user's manuals), starts to preheat；

Open ADRC computers and enter windows operating systems, check computer system time, modify if necessary. Check hard disc of computer residue 1G space above；

Check ADRC computers C:\WINADRAC、C:Whether there is previous examination in two files of RHOTEMP and ADRC drawers Test and last data and recording sheet, be such as related previous test personnel, correct backup and cleaning；

Load associated documents, kit bag, flat mouth screwdriver, duplicated record paper/pen and label patch in ADRC drawers, wherein Following object can be included in kit bag：TEST signal wires * 1, BNC-4mm adapters * 2, BNC rods move cap signal (box) * 1, BNC-UHF adapters * 1；

Test cycle file " AAXCXX " is established under C disks, and (wherein " AA " is power station name, and " X " is machine group number and circulation Number), such as：" GD1C15 ", " LA1C10 ", " LA3C02 "；

Will " new start-up parameter file copy below in Design Data " to C using ADRC special-purpose USB flash disks:\WINADRAC Most newly-established " AAXCXX " two files, including adrc.ndr (neutronics Parameter File) and bank_XX.dsn (dynamics Rod factor file is carved, wherein XX is control rod title, and dynamic carves rod function and needs to call)；

Rod is carved as Mobile state need to be entered, confirms that all bank_XX.dsn file names and form correctly (refer to ADRC user's hand Volume), selective examination bank_XX.dsn file contents with《Dynamic carves rod factor file》Unanimously；

ADRC special-purpose USB flash disks are temporarily accommodated in ADRC drawers；

Confirm software information and licensing；

" ADRC " icon of computer desktop is clicked on, starts software, records ADRC software versions；

Confirm that Configuration Control presentation of information is consistent with ADRC user's manuals；

Confirm License information.Rod is carved as Mobile state need to be entered, DRWN functions should be included；

Confirm Copyright information；

Check Nuclear Design Data and《Startup physics test is reported》Unanimously, confirm that unit and cyclical information (will Label as all test datas afterwards) correctly, modify and record if necessary；

Cold Start are selected to carry out system initialization；

Record C:WINADRAC catalogue file inventories；

MS-DOS (operation " cmd ") is opened, path goes to C:WINADRAC catalogues (key in " cdC:\WINADRAC”)；

Generate lists of documents in catalogue and (key in " dir>winadrc.txt”)；

Exit MS-DOS (click on and close or key in " exit ")；

Print C:Winadrc.txt files in WINADRAC files；

Delete C:Winadrc.txt files in WINADRAC files.

Step S502：Functional check is with setting before startup.

In this step, for functional check, the CHECK functions in ADRC main menu (Main Menu) are selected, at it In：Perform IEEE and examine (Verify IEEE Hardware Operational), confirmation is all effective in fortune instrument, performs hard Part self-test (Perform Hardware Self-Tests), confirm all effective in fortune instrument；Examine and determine digital multimeter (Digital Multimeter Verification)；Examine and determine pico-ampere table/current source (Picoammeter/Source Verification)；Carry out digital-to-analogue conversion output and examine (Digital to Analog Output Verification)；Enter Four recorder calibratings (Strip Chart Recorder Verification) of row；Carry out rod and move logic board inspection (SLC Logic Card Verification)；Exit ADRC CHECK functions.

Then high voltage control inspection is carried out, selects the CALIBRATE functions in ADRC main menu (Main Menu), will High-voltage power supply output is set to ON, and " HV Voltage Ramp Up " confirm that high-voltage power supply output progressively increases to high pressure limit, wait for execution Some time, " HV Voltage Ramp Down " confirmed that 0V is progressively down in high-voltage power supply output, by high-voltage power supply as performed after 5 minutes Output is set to OFF.Certainly, if inapplicable ADRC High voltage output functions, directly close high-voltage power supply, examined without high voltage control Test.

In this step, for function setting, the SETUP functions in ADRC main menu (Main Menu) are selected, are inputted The PRC probe access number (such as " CH1 ") of selection, configuration digital multimeter (Configure Digital Multimeter (s) analog output channel (Configure Analog Output Channels)), is configured, carries out the passage of four recorders Set, carry out neutronics parameter testing (Input Nuclear Design Data), calculate analytical parameters input (Input ANALYZE Function Parameters), exit ADRC SETUP functions.

In step S502, also enter row index test, adder inspection, arrange vanning and live functional check with Signal connects.

When index is tested, set four recorder reactivity passages physical extent (as be -100~+100pcm) and Chart drive speed (such as 10mm/min), throw pen and open paper feed record, in the main menu (Main Menu) for selecting ADRC CALIBRATE functions, perform " Perform Internal Exponential Test " progress (such as+100 seconds cycles) refer to Number test, four recorder Flux and Rho (Top) are confirmed for normal tracking registration, and T-avg and L-pzr registrations are default Lower limit, wait it is to be tested terminate automatically, stop four recorder paper feeds record, the absolute skin of exact p-value result receives difference and is less than predetermined model Enclose as 0.5% and there is no error message, at the same test reaction result and《Startup physics test is reported》What is provided is reactive Absolute deviation is less than predetermined value such as 0.5%, recovers the physical extent and recovery chart drive speed of four recorder reactivity passages, Then the index such as -250 seconds cycles is carried out to test, it is to be tested to terminate rear exact p-value result absolute deviation automatically and be less than predetermined value As 0.5% and there is no error message, ADRC CALIBRATE functions are exited.

When carrying out adder inspection, prepare the dynamic letter of universal meter, BNC-UHF adapters, BNC-4mm adapters and BNC rods Number cap, adder insulating properties inspection is carried out, i.e., is connected BNC-UHF adapters, TEST signal wires and BNC-4mm adapters Adder output is connected to, then with the resistance under universal meter measurement adder open circuit, then carries out adder conduction inspection Look into, i.e., BNC-UHF adapters and the dynamic cap signal of BNC rods are connected to an input for being connected to adder, use universal meter Measure the resistance under adder short circuit.

Arrange case when, into ADRC RHO functions, select Options menus " Scale Reactivity ", really The scale and zero offset for recognizing reactivity are set, and are exited ADRC and are closed each parts of ADRC, close ADRC general supplies, disconnection connects Line, calibrating voltage source, computer, mouse, printer, power line and data wire etc. are rationally cased, close ADRC case lids, so Cable box is opened afterwards and checks TOP, the UHF joint cleannes at tri- cable both ends of BOTTOM, HIGH VOLTAGE, is entered if needed Row cleaning, recovers joint protective sleeve after inspection, closing lid of casing.

When functional check is connected with signal at the scene, first carry out field wiring with check, then carry out mean temperature and Voltage-stablizer water level signal connects, and then carries out PRC cable connections, sets probe high pressure, and set background to compensate electric current, most postscript Record file printout.

When wiring is with checking at the scene, ADRC rack case lids are opened, check the gas of handling process one whether there is damage or loosened, such as It is necessary to be recovered；ADRC computers are taken out, check handling process whether there is damage；Check UHF joint cleannes；From cable box Tri- BOTTOM, HIGH VOLTAGE cables are taken out, remove UHF joint protective sleeves and cable tie, and be accommodated in ADRC drawers；Lay this three cables；Correct connection each parts of ADRC, open all appts and start to preheat；It is soft to run ADRC Part, order perform a functional check (i.e. IEEE inspection, hardware check, digital multimeter is examined and determine, pico-ampere table/current source is examined and determine, Digital-to-analogue conversion output is examined, four recorder calibratings, rods move logic board and examined), time function setting of sequential search (confirms The PRC probe access number that scene is selected is consistent with the channel number inputted, checks digital multimeter configuration, checks that simulation output is led to Road configures, and checks that four recorders are set, checks neutronics parameter, checks and calculate analytical instrument), -100 seconds cycles are carried out respectively Tested with the index in -350 seconds cycles, check that scale reactive in RHO patterns is set with zero offset.

In mean temperature connects with voltage-stablizer water level signal, confirm that the connection of Startup physics test signal box signal is complete Into from Startup physics test signal box extraction primary Ioops mean temperature (T-avg) signal, access ADRC, from Startup physics test Signal box draws voltage-stablizer water level (L-pzr) signal, accesses ADRC, ADRC RHO functions is run, according to software window and four Whether the wiring of T-avg and L-pzr registrations confirmation signal is correct in recorder.

In PRC cable connections, confirm to have completed the switching of PRC racks signal transmission, i.e. signal Delivered master control room, Allow to connect PRC signal cables；Rod is carved as Mobile state need to be entered, PRC probe high voltage supply switchings have been completed in confirmation, it is allowed to which connection is high Voltage cable；Hardware is in opening used in ADRC；Foregoing three cable connections are got well and check insulating properties, are checked ADRC pico-amperes represent number, confirm that cable connection is correct.

Rod is carved as Mobile state need to be entered, it is necessary to uses ADRC High voltage outputs.In probe high pressure is set, confirm to allow by ADRC High-voltage power supply supply PRC probe high pressures, check that voltage is often walked in the script file of High voltage output control increases (subtracting) amount and high pressure limit It is consistent with field requirement, high-voltage power supply and warmed-up enough time are opened, the CALIBRATE functions of ADRC main menu is selected, holds " HV Voltage Ramp Up ", high-voltage power supply progressively boost to high pressure limit to row automatically.

Rod is carved as Mobile state need to be entered, it is necessary to sets background to compensate electric current.In the setting of background compensation electric current, PRC is confirmed Cable connection and probe high pressure set and completed；ADRC connections run and supply PRC probe the high pressure some time such as 30 minutes with On；Confirm operation of the following some time as reactivity will not be changed for 30 minutes；Select the CHECK of ADRC software main menus Function, pico-ampere table/current source detection is performed, select the CALIBRATE functions of ADRC software main menus, select background current true Fixed/compensation function, perform and set background to compensate electric current, after automatic spring result, click continues to automatically begin to perform automatic tune Whole background current, destination file is ejected after automatic setting terminates, confirm errorless rear closing, click on and complete to set, according to ADRC Pico-ampere table and current source registration confirm background current, and such as current anomaly checks whether high pressure setting, connection, reactor core state etc. close It is suitable, reset if necessary.

Step S503：Removed after experiment.

In this step, high-voltage power supply is progressively first down to 0V automatically, exits ADRC, close remaining institute in addition to ADRC computers With instrument, cleaning backup experiment lasts data, sorting and file historgraphic data recording paper, first closes ADRC computers, be then shut off ADRC general supplies；The connection of PRC cables and ADRC interfaces is first disconnected, is then turned off the connection of PRC cables and master control room interface；It is extensive Multiple PRC probes high pressure amounts to and the transmission of PRC racks signal, disconnects the connection of T-avg and L-pzr signals and ADRC interfaces, removes ADRC power lines and data wire, by the reasonable vanning closing lid such as PRC cables, computer, transport storehouse back.

The present embodiment combines the setting and inspection that specific nuclear power station feature establishes the advanced reactivity meter for dynamically carving rod Checking method, advanced reactivity meter normal work and can obtain correct reactivity measurement value during ensureing field test.

To sum up each embodiment, rod field conduct method is carved using nuclear power station provided by the invention dynamic, dynamic can be caused Rod is carved to have the following advantages that：1. every group of control rod all independently measures, without interference effect, rod is worth the valency independent of reference bar Value, measurement result reliability are high；2. whole measurement process does not have boronation dilution operation, the maximum reactivity that measurement process can reach It is safer depending on the reactivity of original state (ARO states)；3. measuring simple to operate, it is general that mistake is greatly lowered Rate；4. the control rod worth using position as function can be provided, there is provided the reactor core required for more data verification safety analyses Calculation model for design；5. improving measurement efficiency, reduce one passage disabled time of RPN power range, each overhaul In significantly save overhaul critical path time at least more than ten hour；6. reduce the movement of control rod and the row of radwaste Put.

Above content is to combine specific embodiment further description made for the present invention, it is impossible to assert this hair Bright specific implementation is confined to these explanations.For general technical staff of the technical field of the invention, do not taking off On the premise of from present inventive concept, some simple deduction or replace can also be made.

Claims

1. a kind of nuclear power station dynamic carves the three-dimensional effect modification method of rod, it is characterised in that including：

By the signal of the signal of upper detector and bottom detector difference divided by the corresponding Static-state Space factor, top spy is obtained Survey the amplitude function of device and the amplitude function of bottom detector, the simulation static probes when Static-state Space factor is plunger The ratio of simulation static probes signal when signal is extracted out with full rod；

The amplitude function of the upper detector and the amplitude function of bottom detector are adjusted to identical in the value of zero moment, will The amplitude function of upper detector after adjustment and the amplitude function of bottom detector are input to a heap dynamics side after being averaged Cheng Zhong, obtain the dynamic rod value of control rod；

The dynamic space factor amendment dynamic determined according to dynamic rod value carves the three-dimensional effect of rod, wherein the dynamic Steric factor is the ratio of static rod value and dynamic rod value；

Pile reactivity initial level is 50-75PCM in the nuclear power station, control rod translational speed is 72 steps/minute, initial Flux is the 75% of Doppler's heat generating spot.

2. nuclear power station dynamic as claimed in claim 1 carves the three-dimensional effect modification method of rod, it is characterised in that the amendment is dynamic The three-dimensional effect that state carves rod includes：Final control rod worth is calculated, the final control rod worth is that the dynamic is empty Between the factor and the dynamic rod value product.