CN103514967A - Intelligent reactor control method - Google Patents
Intelligent reactor control method Download PDFInfo
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- CN103514967A CN103514967A CN201210201313.4A CN201210201313A CN103514967A CN 103514967 A CN103514967 A CN 103514967A CN 201210201313 A CN201210201313 A CN 201210201313A CN 103514967 A CN103514967 A CN 103514967A
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- phi
- neutron
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- lambda
- fluence rate
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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
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to an intelligent reactor control method sequentially comprising the steps that: 1, parameters are collected; 2, neutron fluence rate of the reactor is sampled; 3, the neutron fluence rate is subjected to average processing with a calculation time interval delta t, such that average neutron fluence rate phi of each time point is obtained; 4, an intermediate variable of the t time is obtained; 5, a reactivity of the t time is obtained; 6, a neutron fluence rate expectation value of a t+1 time is set, such that intermediate variable of t+1 second is obtained; 7, the virtual reactivity of the t+1 time is obtained; 8, a control rod adjustment amount of the t+1 time is obtained; and 9, steps of a stepper motor driving the control rod is obtained. With the method provided by the invention, the control manner completely satisfies an objective law of reactor power growth or attenuation. During actual application, a stable value can be rapidly achieved according to a preset operation curve, such that overshoot and ringing caused by over-adjustment are avoided. During stable operation, neutron fluence rate can be stabilized within 0.3% under control.
Description
Technical field
The present invention relates to a kind of intelligent response heap control method, particularly relate to a kind of intelligent response heap control method for meeting kinetics equation reactor.
Background technology
Traditional reactor control theory is according to current industry control PID(ratio, integration, differential) regulate, present most of reactor control systems are all according to this theory design, and do not take the inherent characteristic of reactor capability increase and decrease into account.
Regardless of different kinds of any reactor, all can move according to reactor kinetics equation, according to reactor kinetics equation, can accurately calculate current reactivity, if can set power or the neutron fluence rate of next second, adopt identical computing method just can calculate reactive variable quantity, and then the regulated quantity of controlled rod, calculate and make control rod run to accurate desired location in real time, make the real power of next second can approach very much predetermined value.This control model and traditional control model are very different, classic method only regulates the lifting of control rod according to the difference of performance number and setting value, and new control model has default intelligence, make the power of reactor reach fast and be stabilized in setting value, thereby avoided overshoot overshoot and vibration.Therefore need badly a kind of novel intelligent response heap control method is provided.
Summary of the invention
The technical problem to be solved in the present invention is to provide a kind of intelligent response heap control method that makes reactor reach fast stationary value.
For solving the problems of the technologies described above, intelligent response heap control method of the present invention, comprises the following steps successively:
The first step, gathers following parameter;
λ
ithe disintegration constant of-i group delayed-neutron precursor; Unit is s
-1; Totally 15 groups;
β
effeffective share that-delayed neutron is total;
β
ieff-i organizes effective delayed neutron fraction, totally 15 groups;
Λ-neutron generation time; Unit is s;
The outer neutron source strength of Q-; Unit is neutron/s;
γ
sthe relative worth of-outer neutron source;
The efficiency of ε-outer neutron source;
K
hthe step-length of the stepper motor of-driving control rod, unit is mm/ step;
Intermediate variable
Intermediate variable
Intermediate variable
Wherein: Δ t is interval computing time; a
i=β
ieff/ β
eff;
Second step, samples to the neutron fluence rate of reactor;
The 3rd step, in computing time interval of delta t, averages processing to neutron fluence rate, obtains each average neutron fluence rate Φ constantly;
The 4th step, obtains t intermediate variable I constantly
i(t);
I
i(t)=I
i(t-1)·A
i+Φ(t)·B
i-Φ(t-1)·C
i;
i=1~15;I
i(0)=0;
The 5th step, obtains t reactive ρ (t) constantly;
The 6th step, sets t+1 neutron fluence rate expectation value Φ constantly
v(t+1), obtain the t+1 intermediate variable I of second
vi(t+1);
I
vi(t+1)=I
i(t)·A
i+Φ
v(t+1)·B
i-Φ(t)·C
i;
i=1~15;
The 7th step, obtains t+1 virtual reactive ρ constantly
v(t+1);
The 8th step, obtains the regulated quantity Δ H of t+1 control rod constantly;
The 9th step, obtains driving the step number N of the stepper motor action of control rod;
Δt=1s。
The invention enables control mode to meet the objective law of reactor-up or decay completely, this rule is difficult to common PID(ratio, integration, differential) regulate and realize, in actual use, can reach fast stationary value according to default operation curve (comprise and increase or reduce power), overshoot and the concussion of having avoided overshoot to cause, when stable operation, the present invention can compensate external interference rapidly and accurately, and neutron fluence rate is stabilized in 0.3%.See Fig. 1.
Accompanying drawing explanation
Fig. 1 is neutron fluence rate lifting curve figure.
Embodiment
Below in conjunction with drawings and Examples, the present invention is further detailed explanation.
The basis of this patent is to have adopted stepper motor to drive control rod lifting, makes the control accuracy of control rod within 0.2mm, and so just making accurately to control reactor according to reactivity becomes possibility.
The present invention comprises the following steps successively:
The first step, gathers following parameter;
λ
ithe disintegration constant of-i group delayed-neutron precursor; Unit is s
-1; Totally 15 groups;
β
effeffective share that-delayed neutron is total;
β
ieff-i organizes effective delayed neutron fraction, totally 15 groups;
Λ-neutron generation time; Unit is s;
The outer neutron source strength of Q-; Unit is neutron/s;
γ
sthe relative worth of-outer neutron source;
The efficiency of ε-outer neutron source;
K
hthe step-length of the stepper motor of-driving control rod, unit is mm/ step;
Intermediate variable
Intermediate variable
Intermediate variable
Wherein: Δ t is interval computing time, preferred Δ t=1s; a
i=β
ieff/ β
eff;
the differential efficiency of-control rod, is obtained in advance by Physical Experiment; Unit is mk/mm;
Second step is sampled to the neutron fluence rate of reactor on time, and the sample frequency of ADC is 5000 times/second, and every 50ms uploads to PC after neutron fluence rate data are averaged; This sampling is circulation execution incessantly on time;
The 3rd step, in computing time interval of delta t, averages processing to neutron fluence rate, obtains each average neutron fluence rate Φ constantly; Preferred Δ t=1s;
The 4th step, obtains t intermediate variable I constantly
i(t);
I
i(t)=I
i(t-1)·A
i+Φ(t)·B
i-Φ(t-1)·C
i;
i=1~15;I
i(0)=0;
The 5th step, obtains t reactive ρ (t) constantly;
The 6th step, sets t+1 neutron fluence rate expectation value Φ constantly
v(t+1), obtain the t+1 intermediate variable I of second
vi(t+1);
I
vi(t+1)=I
i(t)·A
i+Φ
v(t+1)·B
i-Φ(t)·C
i;
i=1~15;
The 7th step, obtains t+1 virtual reactive ρ constantly
v(t+1);
The 8th step, obtains the regulated quantity Δ H of t+1 control rod constantly;
The 9th step, obtains driving the step number of the stepper motor action of control rod;
Claims (2)
1. intelligent response is piled control method, comprises the following steps successively:
The first step, gathers following parameter;
λ
ithe disintegration constant of-i group delayed-neutron precursor; Unit is s
-1; Totally 15 groups;
β
effeffective share that-delayed neutron is total;
β
ieff-i organizes effective delayed neutron fraction, totally 15 groups;
Λ-neutron generation time; Unit is s;
The outer neutron source strength of Q-; Unit is neutron/s;
γ
sthe relative worth of-outer neutron source;
The efficiency of ε-outer neutron source;
K
hthe step-length of the stepper motor of-driving control rod, unit is mm/ step;
Intermediate variable
Intermediate variable
Intermediate variable
Wherein: Δ t is interval computing time; a
i=β
ieff/ β
eff;
the differential efficiency of-control rod; Unit is mk/mm;
Second step, samples to the neutron fluence rate of reactor;
The 3rd step, in computing time interval of delta t, averages processing to neutron fluence rate, obtains each average neutron fluence rate Φ constantly;
The 4th step, obtains t intermediate variable I constantly
i(t);
I
i(t)=I
i(t-1)·A
i+Φ(t)·B
i-Φ(t-1)·C
i;
i=1~15;I
i(0)=0;
The 5th step, obtains t reactive ρ (t) constantly;
The 6th step, sets t+1 neutron fluence rate expectation value Φ constantly
v(t+1), obtain the t+1 intermediate variable I of second
vi(t+1);
I
vi(t+1)=I
i(t)·A
i+Φ
v(t+1)·B
i-Φ(t)·C
i;
i=1~15;
The 7th step, obtains t+1 virtual reactive ρ constantly
v(t+1);
The 8th step, obtains the regulated quantity Δ H of t+1 control rod constantly;
The 9th step, obtains driving the step number N of the stepper motor action of control rod;
2. intelligent response heap control method according to claim 1, is characterized in that: described Δ t=1s.
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CN201210201313.4A CN103514967B (en) | 2012-06-15 | 2012-06-15 | Intelligent response heap control method |
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CN103514967B CN103514967B (en) | 2016-03-02 |
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Citations (7)
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---|---|---|---|---|
CN1043032A (en) * | 1988-11-14 | 1990-06-13 | 法玛通公司 | The reactor of the control method of pressurized-water reactor and this method of enforcement |
JPH0227639B2 (en) * | 1980-08-22 | 1990-06-19 | Hitachi Ltd | |
JPH06201877A (en) * | 1992-12-28 | 1994-07-22 | Hitachi Ltd | Automatic reactor control rod operation device |
KR20010114106A (en) * | 2000-06-21 | 2001-12-29 | 장인순 | Dissipation Method of Coil Energy of Control Element Drive Mechanism for Nuclear Reactor |
CN101840737A (en) * | 2009-09-02 | 2010-09-22 | 中广核工程有限公司 | Digital rod position control system and method |
US20110110477A1 (en) * | 2009-11-06 | 2011-05-12 | Searete Llc, A Limited Liability Corporation Of The State Of Delaware | Systems and methods for controlling reactivity in a nuclear fission reactor |
CN102306508A (en) * | 2011-09-07 | 2012-01-04 | 中国核动力研究设计院 | Reactivity instrument for critical monitoring and critical extrapolation of reactor |
-
2012
- 2012-06-15 CN CN201210201313.4A patent/CN103514967B/en active Active
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0227639B2 (en) * | 1980-08-22 | 1990-06-19 | Hitachi Ltd | |
CN1043032A (en) * | 1988-11-14 | 1990-06-13 | 法玛通公司 | The reactor of the control method of pressurized-water reactor and this method of enforcement |
JPH06201877A (en) * | 1992-12-28 | 1994-07-22 | Hitachi Ltd | Automatic reactor control rod operation device |
KR20010114106A (en) * | 2000-06-21 | 2001-12-29 | 장인순 | Dissipation Method of Coil Energy of Control Element Drive Mechanism for Nuclear Reactor |
CN101840737A (en) * | 2009-09-02 | 2010-09-22 | 中广核工程有限公司 | Digital rod position control system and method |
US20110110477A1 (en) * | 2009-11-06 | 2011-05-12 | Searete Llc, A Limited Liability Corporation Of The State Of Delaware | Systems and methods for controlling reactivity in a nuclear fission reactor |
CN102306508A (en) * | 2011-09-07 | 2012-01-04 | 中国核动力研究设计院 | Reactivity instrument for critical monitoring and critical extrapolation of reactor |
Non-Patent Citations (2)
Title |
---|
沈峰等: "ADS次临界反应堆的点堆中子动力学方程", 《原子能科学技术》 * |
赵柱民等: "脉冲堆反应性测量系统的研制", 《中国核科技报告》 * |
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Address after: 102413 Beijing city Fangshan District town No. 3 North Street No. 18 hospital Patentee after: Beijing kaibaite Polytron Technologies Inc Address before: 102413 Beijing city Fangshan District town No. 3 North Street No. 18 hospital Patentee before: Beijing Kai Baite Science and Technology Ltd. |