CN110033871A - A kind of control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station - Google Patents
A kind of control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station Download PDFInfo
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- CN110033871A CN110033871A CN201910192202.3A CN201910192202A CN110033871A CN 110033871 A CN110033871 A CN 110033871A CN 201910192202 A CN201910192202 A CN 201910192202A CN 110033871 A CN110033871 A CN 110033871A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The present invention provides a kind of control methods of the pressurized water reactor initial criticality at million kilowatt nuclear power station, comprising the following steps: after reactor refuling processing, carries out rod withdrawal processing, makes 170 step of most terminal ledge position of R stick, the most terminal ledge position of other sticks is 225 steps;After rod withdrawal processing, processing is diluted to reactor core, as CB (mes)=CB during neutron counts down rate=0.1 or primary IoopsCRI extrapolationWhen either condition in+10ppm meets, stop dilution processing;Stick position >=150 steps of R stick are adjusted, until reaching initial criticality.The control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station provided by the invention, effectively thoroughly solving the problems, such as after reloading that reactor mentions R stick still cannot be once successfully up to critical from 170 steps to top (referred to as " once mentioning R stick ").
Description
Technical field
The invention belongs to nuclear reactor art field more particularly to a kind of pressurized water reactors at million kilowatt nuclear power station for the first time
Critical control method.
Background technique
Pressurized water reactor is a kind of light-water nuclear reactor, in the pressurized water reactor course of work, with the progress of nuclear reaction, core
Raw material gradually uses up, and therefore, it is necessary to add part material, that is, carries out processing of reloading.According to nuclear safety codes " reactor after reloading
First divergence is implemented and (carves stick technology using dynamic) " requirement of (CTSFUL052), initial criticality after pressurized water reactor reloads
In test procedure, physical test personnel critical operation standard hot shutdown condition after reactor refuling first carries out rod withdrawal behaviour
Make (most terminal ledge position: R=170 step, other 225 steps of stick), is diluted later to neutron and is counted down rate (N0/ N)=0.1 or boron it is dense
Spend (CBmes)=CBIt is theoretical+ 30ppm stop immediately (the two either condition first meet then immediately stop dilution, wherein CBmes refers to
Actually measured boron concentration value;CBIt is theoreticalRefer to and is simulated based on model, the theoretical boron concentration value being calculated), finally mention R stick
(manipulation stick) reaches critical.When reactor reach for the first time it is critical after require R stick critical rod position not in 150~190 steps when, it is desirable that adjustment
To the value > 100pcm of R stick insertion reactor core.The adjustment of stick reactor core original state is carved in the dynamic of subsequent zero power physics testing
The value ≈ 60pcm of Shi Yaoqiu: R stick insertion reactor core.In actual operation, due to the limitation of dilution stop condition, repeatedly cause
R stick can not once be mentioned up to critical.And the requirement of R stick initial criticality stick position carves stick original state R stick position with dynamic later
Requirement mutually conflict, therefore, when R stick once mention 225 steps still can not be critical when, need to turn back to 170 steps, it is dilute to increase small flow
It releases, repeatedly attempts to mention R stick up to critical, or even duplicate and mention R clubs work three times and just successfully realize critical, cause to occur first diluting
The operation repeatedly of boronation after again, increases waste liquid amount and test period.
75 times provided according to Daya bay base are up to critical data statistics (cut-off in August, 2017), wherein fail for 10 times primary
R stick is mentioned up to critical, details see the table below 1:
Table 1
Fail once to mention R stick to above-mentioned and analyzed up to critical situation, generally existing following general character: dilution one
Circuit boron concentration C B (mes)=CBIt is theoretical+ 30ppm, dilution stop, and neutron counts down (the i.e. stopping item of boron concentration of rate > 0.1 at this time
Part is first more up to standard than the neutron rate stop condition that counts down), R stick reactor is mentioned again after increasing small flow dilution up to critical.Thus
As it can be seen that dilution has stopped too early (the practical amount of dilution of first time is inadequate), with CB (mes)=CBIt is theoreticalThe stopping of+30ppm is dilute
It is overly conservative to release condition control.Due to nuclear design software, the precision of measuring instrument and uniformity coefficient of primary Ioops boron concentration etc.
Factor influences, and leads between measured result and theoretical boron concentration results that there are certain deviations.Daya bay base Hot zero power institute
The deviation situation of critical boron concentration measured value and theoretical value counts as shown in Figure 1 in the case of having control rod to mention entirely, wherein GNPS,
LNPS, LNPS-II respectively indicate Daya Gulf unit, ridge Australia one phase unit and ridge Australia second level unit.It can be seen from figure 1 that Daya Gulf machine
The ridge Zu He Australia one phase unit HZP-ARO (reactor is in zero energy, primary Ioops RCP temperature be in (289.4 DEG C, 294.4
DEG C), all control stick positions are in 225 steps) state critical boron concentration measured value slightly have compared with theoretical value it is bigger than normal or suitable;The ridge Australia second phase
The HZP-ARO state critical boron concentration measured value of unit is less than normal compared with theoretical value more, average 30ppm less than normal.When HZP-ARO state
The differential value of boron is about -7pcm/ppm, and the corresponding about 210pcm of 30ppm is reactive, and the value of R stick 170 step to 225 steps is limited
(generally about 250pcm).Ridge Australia second phase unit dilution approach to criticality process stops dilution in CB (mes)=CBCAL+30ppm,
It is superimposed measured result again compared with the universal corresponding about 210pcm of relatively low 30ppm of theoretical value, causes once to mention R stick being insufficient to compensate for up to critical
Required reactivity causes once propose the critical success of R stick.
Summary of the invention
The purpose of the present invention is to provide the control methods that a kind of pressurized water reactor reaches amount of dilution in critical process, it is intended to solve
Certainly in the prior art, pressurized water reactor once mentions R stick up to the problem of critical unsuccessful, R stick critical rod position adjusts repeatedly.
For achieving the above object, The technical solution adopted by the invention is as follows:
The present invention provides a kind of control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station, including following
Step:
After reactor refuling processing, rod withdrawal processing is carried out, 170 step of most terminal ledge position of R stick, the most terminal ledge position of other sticks are made
For 225 steps;
After rod withdrawal processing, processing is diluted to reactor core, as CB during neutron counts down rate=0.1 or primary Ioops
(mes)=CBCRI extrapolationWhen either condition in+10ppm meets, stop dilution processing, wherein CB (mes) is actually measured one time
Boron concentration value in road, CBCRI extrapolationFor extrapolation criticality boron concentration;
Stick position >=150 steps of R stick are adjusted, until reaching initial criticality.
Further, stick position >=150 steps of the adjustment R stick, until in the step of reaching initial criticality, including following step
It is rapid: to detect whether to reach critical state, if keeping the stick invariant position of R stick up to critical after dilution processing;If not having after dilution processing
Up to critical, then the stick position of R stick is mentioned to >=150 steps, until reaching initial criticality.
Further, stick position >=150 steps of the adjustment R stick, until in the step of reaching initial criticality, when dilution is handled
It is overcritical afterwards, and when stick position 150 step of < of R stick, rod withdrawal processing is carried out to R stick, while improving the boron concentration in primary Ioops, until
The stick position of R stick >=150 steps.
Further, in the step of boron concentration improved in primary Ioops, boric acid is added with 500L/ hours rates of <
Aqueous solution, until the stick position of R stick is mentioned to >=150 steps.
Further, stick position >=150 steps of the adjustment R stick, until in the step of reach initial criticality, when mentioning R stick
Behind stick position to 225 steps, when still not reaching critical state, the stick position of underthrust R stick to 170 steps;Then it is diluted place again
Reason, until reaching initial criticality.
Further, described to be diluted processing again, until in the step of reaching initial criticality, in record dilution processing
N0/ N determines whether to reach critical by aircraft pursuit course.
Further, the N in the record dilution processing0In the step of/N, primary dilution processing is recorded within every 2~5 minutes
In N0/ N determines whether to reach critical by aircraft pursuit course.
Further, the CBCRI extrapolationTest method it is as follows:
In dilution, the neutron of constant duration acquisition actual measurement counts down rate and boron concentration, utilizes nearest two
Measurement point carries out linear extrapolation, obtains extrapolation criticality boron concentration C BCRI extrapolation。
Further, the neutron of constant duration acquisition actual measurement count down rate and boron concentration the step of in, every 10
The neutron once surveyed is acquired within~20 minutes to count down rate and boron concentration, and every time acquisition neutron count down rate and boron concentration when
Between interval holding it is consistent.
Further, after the step of stopping dilution processing, further include the stable system processing after diluting, make
CB(primary Ioops)-CB(voltage-stablizer)< 20ppm, wherein CB(primary Ioops)For the boron concentration in primary Ioops, CB(voltage-stablizer)For the boron concentration in voltage-stablizer.
The control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station provided by the invention optimizes to reach and face
Boundary's process dilutes the control standard (i.e. dilution processing stopping criterion) that water stops and R stick initial criticality stick position requires, effectively thorough
Bottom solves the problems, such as after reloading that reactor mentions R stick still cannot be once successfully up to critical from 170 steps to top (once mentioning R stick).
By the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station provided by the invention, it to be used for Daya bay base 6
Platform unit efficiently solves the problems, such as once to reduce boronation up to critical unsuccessful after implementation, dilution operates and mention repeatedly slotting R stick
Number, accordingly reduce the yield of waste liquid and the workload of testing crew, while also reducing equipment fault and maloperation
Risk, it is effective improve unit operation level of security and economic level.The results show that L406, D219, L214,
(wherein, number front two indicates unit, specifically, L1 indicates that one phase of ridge Australia unit, L2 indicate ridge Australia two by D119, L115, L308
Phase unit, L3 indicate that three phase of ridge Australia unit, L4 indicate that ridge Australia fourth phase unit, D1 indicate that one phase of Daya Gulf unit, D2 indicate big sub-
Gulf second phase unit;Two indicate the number that reloads after number.As L406 indicates to reload for ridge Australia fourth phase unit the 6th time) overhaul starting object
Using the critical rod position of standard control R stick in reason test, thoroughly solves R stick critical rod position and adjust situation repeatedly.Only consider
One subcritical unsuccessful the second stage of two units of the frequent ridge Australia of generation, are greatly decreased the operation of marginal test present invention about
50%, human-equation error and relevant accident risk are reduced, overhaul critical path time is substantially saved and be averaged 5 hour/time overhauls, it is latent
It is about 93,000,000 yuan in income.
Detailed description of the invention
Fig. 1 is critical boron concentration in the case of all control rods of Daya bay base Hot zero power that the prior art provides mention entirely
The deviation situation statistical chart of measured value and theoretical value.
Specific embodiment
In order to which technical problems, technical solutions and advantageous effects to be solved by the present invention are more clearly understood, below in conjunction with
Embodiment, the present invention will be described in further detail.It should be appreciated that specific embodiment described herein is only used to explain
The present invention is not intended to limit the present invention.
In the description of the present invention, it is to be understood that, term " first ", " second " are used for description purposes only, and cannot
It is interpreted as indication or suggestion relative importance or implicitly indicates the quantity of indicated technical characteristic.Define as a result, " the
One ", the feature of " second " can explicitly or implicitly include one or more of the features.In the description of the present invention,
The meaning of " plurality " is two or more, unless otherwise specifically defined.
The embodiment of the present invention provides a kind of control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station, packet
Include following steps:
S01. after reactor refuling processing, carry out rod withdrawal processing, make 170 step of most terminal ledge position of R stick, other sticks it is final
Stick position is 225 steps;
S02. after rod withdrawal processing, processing is diluted to reactor core, as CB during neutron counts down rate=0.1 or primary Ioops
(mes)=CBCRI extrapolationWhen either condition in+10ppm meets, stop dilution processing, wherein CB (mes) is actually measured one time
Boron concentration value in road, CBCRI extrapolationFor extrapolation criticality boron concentration;
S03. stick position >=150 steps for adjusting R stick, until reaching initial criticality.
The control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station provided in an embodiment of the present invention, optimization
The control standard (i.e. dilution processing stopping criterion) stopped up to critical process dilution water and R stick initial criticality stick position require,
Effectively thoroughly solve reactor after reloading mention R stick still cannot be once successfully up to critical from 170 steps to top (once mentioning R stick)
Problem.By the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station provided in an embodiment of the present invention, it is used for
6 units of Daya bay base efficiently solve the problems, such as once to reduce boronation up to critical unsuccessful after implementation, dilution is grasped repeatedly
The number for making and mentioning slotting R stick, accordingly reduces the yield of waste liquid and the workload of testing crew, while also reducing equipment event
The risk of barrier and maloperation, it is effective to improve the level of security and economic level of unit operation.The results show that L406,
(wherein, number front two indicates unit, specifically, L1 indicates one phase of ridge Australia unit, L2 by D219, L214, D119, L115, L308
Indicate that ridge Australia second phase unit, L3 indicate that three phase of ridge Australia unit, L4 indicate that ridge Australia fourth phase unit, D1 indicate one phase of Daya Gulf unit,
D2 indicates Daya Gulf second phase unit;Two indicate the number that reloads after number.As L406 indicates to reload for ridge Australia fourth phase unit the 6th time)
Using the critical rod position of standard control R stick in overhaul Startup physics test, thoroughly solves R stick critical rod position and adjust feelings repeatedly
Condition.Only consider subcritical unsuccessful the second stage of two units of the frequent ridge Australia of generation, marginal test present invention is greatly decreased
Operation about 50% reduces human-equation error and relevant accident risk, substantially saves overhaul critical path time and is averaged 5 hours/time
Overhaul, potential income are about 93,000,000 yuan.
Specifically, in above-mentioned steps S01, to reaction to the processing that reload after, carry out rod withdrawal processing.Made instead by rod withdrawal
It answers heap reactor core more quickly close to critical state, while guaranteeing that reactor has and quickly coping with control protection by control rod
Ability.Rod withdrawal is handled so that the most terminal ledge position of R stick is 170 steps, and the most terminal ledge position of other sticks is 225 steps.At this point it is possible to reserve part
Gradation Critical Degree can realize the quick and Critical Stability of reactor by reserved control rod worth after dilution.
In above-mentioned steps S02, after rod withdrawal processing, need to be diluted reactor core processing.Specifically pass through dilution
Boron concentration in processing control reaction system, and then achieve the purpose that stabilising system Seed Levels, it is in nuclear reaction and stablizes instead
Answer state.And during diluting approach to criticality, it is unexpected critical to prevent, the situation of change for the rate of counting down need to be paid close attention to, together
When constantly track boron concentration variation.Since boron concentration calculated value inherently has certain deviation, so using CB
(mes)=CBIt is theoreticalStop that diluted judgment criteria is less suitable when+30ppm, and surveys the providing again with one of boron concentration results
Fixed time-lag effect, therefore, it is necessary to be adjusted to existing dilution processing termination criteria.
In the embodiment of the present invention, processing is diluted to reactor core, as CB during neutron counts down rate=0.1 or primary Ioops
(mes)=CBCRI extrapolationWhen either condition in+10ppm meets, stop dilution processing, wherein CB (mes) is actually measured one time
Boron concentration value in road, CBCRI extrapolationFor extrapolation criticality boron concentration.Herein, the foundation for establishing the standard is that the boron in primary standard is dense
Degree is the calculated results, after larger deviation occur in theoretical calculation and field measurement, will lead to and mentions R stick from 170 steps to 225 steps still
Critical success cannot once be reached.It extrapolates, extrapolates using the boron concentration of field measurement and the neutron rate of counting down after adjustment
Result be more nearly field measurement, avoid the relatively large deviation bring between theoretical and field measurement mention R stick from 170 steps to
225 steps still cannot be once successfully up to critical.Advantage adjusted are as follows: what triggering dilution stopped after adjustment is that neutron counts down rate,
It can then guarantee that mentioning R stick may be implemented the initial criticality that once succeeds in the range of from 170 steps to 225 steps.
The embodiment of the present invention is in CBCRI extrapolationOn the basis of, in conjunction with the time-lag effect of boron concentration results, determine with CB (mes)
=CBCRI extrapolationFor+10ppm as one of the standard for stopping dilution processing, the dwell time for diluting processing is more accurate.
Specifically, further, the CBCRI extrapolationTest method it is as follows:
In dilution, the neutron of constant duration acquisition actual measurement counts down rate and boron concentration, utilizes nearest two
Measurement point carries out linear extrapolation, obtains extrapolation criticality boron concentration C BCRI extrapolation.In this way, real-time boron concentration can be obtained,
It realizes measured result zero-deviation, and then the more accurately dwell time of control dilution processing, realizes once up to critical.Further
, the neutron of constant duration acquisition actual measurement count down rate and boron concentration the step of in, acquired one every 10~20 minutes
The neutron of secondary actual measurement counts down rate and boron concentration, and the count down time interval of rate and boron concentration of acquisition neutron keeps one every time
It causes, to guarantee that the stabilization per measured result twice is effective.It in a particular embodiment, can be every the primary actual measurement of acquisition in 15 minutes
Neutron count down rate and boron concentration, utilize two nearest measurement points to carry out linear extrapolation, obtain extrapolation criticality boron concentration
CBCRI extrapolation。
During the embodiment of the present invention is diluted processing to reactor core, the mark of dilution processing dwell time is had adjusted
Standard, since the dwell time of dilution processing is more accurate, subsequent step directly successfully can realize one by adjusting R stick
It is secondary up to critical.Specifically, what triggering dilution stopped is that neutron counts down rate after the standard adjustment of dilution processing dwell time, this
When reactor core can be compensated completely by the value between R stick 170 to 225 apart from critical subcriticality, therefore ensure that and mention R stick
It may be implemented once to mention R stick success initial criticality in the range of from 170 steps to 225 steps.
Further, after the step of stopping dilution processing, further include the stable system processing after diluting, make
CB(primary Ioops)-CB(voltage-stablizer)< 20ppm, wherein CB(primary Ioops)For the boron concentration in primary Ioops, CB(voltage-stablizer)For the boron concentration in voltage-stablizer.
Stablized by system and handled, to accurately learn the dilution gap that treated between state and critical state.It is specific preferred,
The method of stable system processing is, by system uniform 30 minutes or more, obtains dilution treated state.
It, can be by adjusting stick position >=150 steps of R stick, until reaching in dilution after treatment in above-mentioned steps S03
Initial criticality, it is primary to realize up to critical.The establishment of standard, combines the practical experience of history, and new standard can evade solution
After before critical, the unnecessary reciprocal adjustment of R stick caused by primary standard and unnecessary reciprocal dilution and boronation, thus significantly
The unnecessary reactivity operation of reduction, and thus may increased human-equation error and equipment failure, while can substantially save
Overhaul critical path improves the generated energy and economy of power plant while promoting nuclear safety.
In the step, by analysis dilution treated state, detect whether to reach critical state, according to testing result,
It is divided into two kinds of situations and reaches initial criticality.In the first embodiment situation, stick position >=150 steps of the adjustment R stick, until reaching
In the step of to initial criticality, comprising the following steps: detect whether to reach critical state, if protecting after dilution processing up to critical
The stick position (170 stick) for holding R stick is constant, keeps fluxIt is constant.In the first embodiment situation, the stick position of the adjustment R stick
>=150 steps, until in the step of reaching initial criticality, comprising the following steps: detect whether to reach critical state, if dilution is handled
Afterwards up to critical, then the stick position of R stick is mentioned to >=150 steps, until reaching initial criticality.
For second of implementation situation, and it is divided into two kinds of specific embodiments.In certain embodiments, dilution is handled
After detect whether to reach critical state, and if R stick just has in diluting treatment process and becomes up to critical after dilution processing
Change, then mentions the stick position of R stick to reaching initial criticality.At this point, reaching stick position >=170 steps of the R stick of initial criticality.In other realities
It applies in example, detects whether to reach critical state after dilution processing, if it is overcritical after dilution processing, and R stick is in dilution treatment process
In change, stick position is lower than 150 sticks, then mentions the stick position of R stick to reaching initial criticality.At this point, reach the R stick of initial criticality
Stick position >=150 steps.
The control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station provided in an embodiment of the present invention, is used for
Each unit of Daya bay base is able to achieve once up to critical, and marginal test present invention operation about 50% is greatly decreased, reduces
Human-equation error and relevant accident risk substantially save overhaul critical path time and are averaged 5 hour/time overhauls, and potential income is about
It is 93,000,000 yuan.
However, considering that the present invention also provides the embodiments for needing to adjust again from the integrality of technical logic.Specifically
, as a kind of situation, stick position >=150 steps of the adjustment R stick, until in the step of reaching initial criticality, when the stick for mentioning R stick
Position is to after 225 steps, when still not reaching critical state, the stick position of underthrust R stick to 170 steps;Then it is diluted processing again,
Until reaching initial criticality.Preferably, described to be diluted processing again, until being recorded dilute in the step of reaching initial criticality
Release the N in processing0/ N determines whether to reach critical by aircraft pursuit course.Specific preferred, in the record dilution processing N0/
In the step of N, the N in primary dilution processing is recorded within every 2~5 minutes0/ N determines whether to reach critical by aircraft pursuit course.
As another situation, stick position >=150 steps of the adjustment R stick, until in the step of reaching initial criticality, when dilute
It releases overcritical after processing, and when stick position 150 step of < of R stick, rod withdrawal processing is carried out to R stick, while it is dense to improve the boron in primary Ioops
Degree, until stick position >=150 steps of R stick.Further, small with < 500L/ in the step of boron concentration improved in primary Ioops
When rate add boric acid aqueous solution, until the stick position of R stick is mentioned to >=150 steps.Since the rate of addition boric acid aqueous solution is smaller,
It realizes up to critical slower, therefore, it is furthermore preferred that in the step of boron concentration improved in primary Ioops, it is small with 200~250L/
When rate add boric acid aqueous solution, until the stick position of R stick is mentioned to >=150 steps.Most preferably, the boron improved in primary Ioops
In the step of concentration, boric acid aqueous solution was added with 250L/ hours rates, until the stick position of R stick is mentioned to >=150 steps.
Method and standard adjusted are successively in the L406/D219/L214/D119/L115/ in Daya Gulf nuclear power base
Successful implementation in L307 overhaul, realize it is primary successfully up to critical, solve critical rod position standard it is unreasonable cause it is unnecessary
Reciprocal adjustment R stick position and reciprocal dilution and boronation operation, to shorten the generated energy and economy that overhaul critical path promotes power plant
Property contribution it is obvious.
The foregoing is merely illustrative of the preferred embodiments of the present invention, is not intended to limit the invention, all in essence of the invention
Made any modifications, equivalent replacements, and improvements etc., should all be included in the protection scope of the present invention within mind and principle.
Claims (10)
1. a kind of control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station, which is characterized in that including following
Step:
After reactor refuling processing, rod withdrawal processing is carried out, makes 170 step of most terminal ledge position of R stick, the most terminal ledge position of other sticks is
225 steps;
After rod withdrawal processing, processing is diluted to reactor core, when CB (mes) during neutron counts down rate=0.1 or primary Ioops=
CBCRI extrapolationWhen either condition in+10ppm meets, stop dilution processing, wherein CB (mes) is in actually measured primary Ioops
Boron concentration value, CBCRI extrapolationFor extrapolation criticality boron concentration;
Stick position >=150 steps of R stick are adjusted, until reaching initial criticality.
2. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as described in claim 1, feature
It is, stick position >=150 steps of the adjustment R stick, until in the step of reaching initial criticality, comprising the following steps: detect whether
Reach critical state, if keeping the stick invariant position of R stick up to critical after dilution processing;If dilution processing after do not reach it is critical, mention
The stick position of R stick is to >=150 steps, until reaching initial criticality.
3. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as claimed in claim 2, feature
It is, stick position >=150 steps of the adjustment R stick, until in the step of reaching initial criticality, it is overcritical after dilution processing, and R
When stick position 150 step of < of stick, rod withdrawal processing is carried out to R stick, while improving the boron concentration in primary Ioops, until the stick position of R stick >=
150 steps.
4. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as claimed in claim 3, feature
Be, the step of the boron concentration improved in primary Ioops in, boric acid aqueous solution is added with 500L/ hour rates of <, up to R
The stick position of stick is mentioned to >=150 steps.
5. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as claimed in claim 2, feature
It is, stick position >=150 steps of the adjustment R stick, until in the step of reach initial criticality, when mentioning the stick position of R stick to 225 steps
Afterwards, when still not reaching critical state, the stick position of underthrust R stick to 170 steps;Then it is diluted processing again, until reaching
Initial criticality.
6. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as claimed in claim 5, feature
It is, it is described to be diluted processing again, until the N in the step of reaching initial criticality, in record dilution processing0/ N, passes through
Aircraft pursuit course determines whether to reach critical.
7. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as claimed in claim 6, feature
It is, the N in the record dilution processing0In the step of/N, the N in primary dilution processing is recorded within every 2~5 minutes0/ N, passes through
Aircraft pursuit course determines whether to reach critical.
8. the controlling party of the pressurized water reactor initial criticality at million kilowatt nuclear power station as described in any one of claim 1 to 7
Method, which is characterized in that the CBCRI extrapolationTest method it is as follows:
In dilution, the neutron of constant duration acquisition actual measurement counts down rate and boron concentration, utilizes two nearest measurements
Point carries out linear extrapolation, obtains extrapolation criticality boron concentration C BCRI extrapolation。
9. the control method of the pressurized water reactor initial criticality at million kilowatt nuclear power station as claimed in claim 8, feature
Be, the neutron of constant duration acquisition actual measurement count down rate and boron concentration the step of in, acquired every 10~20 minutes
The neutron once surveyed counts down rate and boron concentration, and the count down time interval of rate and boron concentration of acquisition neutron keeps one every time
It causes.
10. the controlling party of the pressurized water reactor initial criticality at million kilowatt nuclear power station as described in any one of claim 1 to 7
Method, which is characterized in that after the step of stopping dilution processing, further include the stable system processing after diluting, make CB(primary Ioops)-
CB(voltage-stablizer)< 20ppm, wherein CB(primary Ioops)For the boron concentration in primary Ioops, CB(voltage-stablizer)For the boron concentration in voltage-stablizer.
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111653373A (en) * | 2020-05-07 | 2020-09-11 | 岭东核电有限公司 | Nuclear power station pressurized water reactor critical test method and system |
CN113257448A (en) * | 2021-04-21 | 2021-08-13 | 广东核电合营有限公司 | Control method and equipment for nuclear power plant reactor extrapolation criticality |
CN113345605A (en) * | 2021-04-29 | 2021-09-03 | 广西防城港核电有限公司 | Fast critical control method for refueling and starting of nuclear reactor |
CN115331844A (en) * | 2022-09-08 | 2022-11-11 | 中国核动力研究设计院 | Method and system for measuring value of control rod under subcritical condition of nuclear reactor |
WO2024050938A1 (en) * | 2022-09-06 | 2024-03-14 | 中广核工程有限公司 | Pressurized water reactor control method and device, computer device and storage medium |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2014106104A (en) * | 2012-11-27 | 2014-06-09 | Mitsubishi Heavy Ind Ltd | Subcriticality measuring method and device |
CN105788666A (en) * | 2014-12-23 | 2016-07-20 | 福建福清核电有限公司 | Nuclear reactor critical process control method |
CN105895174A (en) * | 2016-05-06 | 2016-08-24 | 中国核动力研究设计院 | Method for calculating value of control rod for pressurized water reactor |
CN109256226A (en) * | 2018-11-05 | 2019-01-22 | 三门核电有限公司 | A kind of reactor Critical lattice monitor system and method |
-
2019
- 2019-03-14 CN CN201910192202.3A patent/CN110033871B/en active Active
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2014106104A (en) * | 2012-11-27 | 2014-06-09 | Mitsubishi Heavy Ind Ltd | Subcriticality measuring method and device |
CN105788666A (en) * | 2014-12-23 | 2016-07-20 | 福建福清核电有限公司 | Nuclear reactor critical process control method |
CN105895174A (en) * | 2016-05-06 | 2016-08-24 | 中国核动力研究设计院 | Method for calculating value of control rod for pressurized water reactor |
CN109256226A (en) * | 2018-11-05 | 2019-01-22 | 三门核电有限公司 | A kind of reactor Critical lattice monitor system and method |
Non-Patent Citations (2)
Title |
---|
史永谦: "《核反应堆中子学实验技术》", 31 December 2011, 中国原子能出版社 * |
蔡显岗 等: "某核电站硼稀释达临界模拟分析", 《山东工业技术》 * |
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
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CN111653373A (en) * | 2020-05-07 | 2020-09-11 | 岭东核电有限公司 | Nuclear power station pressurized water reactor critical test method and system |
CN111653373B (en) * | 2020-05-07 | 2022-04-19 | 岭东核电有限公司 | Nuclear power station pressurized water reactor critical test method and system |
CN113257448A (en) * | 2021-04-21 | 2021-08-13 | 广东核电合营有限公司 | Control method and equipment for nuclear power plant reactor extrapolation criticality |
CN113257448B (en) * | 2021-04-21 | 2024-04-19 | 广东核电合营有限公司 | Control method and equipment for reactor extrapolation critical of nuclear power plant |
CN113345605A (en) * | 2021-04-29 | 2021-09-03 | 广西防城港核电有限公司 | Fast critical control method for refueling and starting of nuclear reactor |
CN113345605B (en) * | 2021-04-29 | 2022-12-23 | 广西防城港核电有限公司 | Control method for quickly reaching critical state during refueling and starting of nuclear reactor |
WO2024050938A1 (en) * | 2022-09-06 | 2024-03-14 | 中广核工程有限公司 | Pressurized water reactor control method and device, computer device and storage medium |
CN115331844A (en) * | 2022-09-08 | 2022-11-11 | 中国核动力研究设计院 | Method and system for measuring value of control rod under subcritical condition of nuclear reactor |
CN115331844B (en) * | 2022-09-08 | 2024-04-23 | 中国核动力研究设计院 | Method and system for measuring value of control rod under subcritical nuclear reactor |
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