CN104332200A - Monitoring method for synchronism loss of control rods - Google Patents

Monitoring method for synchronism loss of control rods Download PDF

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Publication number
CN104332200A
CN104332200A CN201310306959.3A CN201310306959A CN104332200A CN 104332200 A CN104332200 A CN 104332200A CN 201310306959 A CN201310306959 A CN 201310306959A CN 104332200 A CN104332200 A CN 104332200A
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CN
China
Prior art keywords
monitoring
control rod
rod
control rods
control
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Pending
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CN201310306959.3A
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Chinese (zh)
Inventor
黄可东
李国勇
田宇
郑杲
金远
许明周
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN201310306959.3A priority Critical patent/CN104332200A/en
Publication of CN104332200A publication Critical patent/CN104332200A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/12Sensitive element forming part of control element
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to control methods of pressurized-water-reactor nuclear power station, and concretely relates to an monitoring method for synchronism loss of control rods of a pressurized-water-reactor nuclear power station. The method comprises the following steps: determining whether the control rods enforce other synchronism-loss alarming, and entering a next step if not; determining whether all control rods in a subgroup/group are at a same position, entering a next step if yes, or else, waiting for all control rods to be at a same position; monitoring whether the position of a first beam of control rods is changed, and recording the current position if yes; and when the above calculation difference exceeds a preset alarming threshold, triggering limit mean value and performing synchronism-loss alarming, or else, entering a next time of cycling. The advantages comprise that by analyzing the difference or the difference absolute value between a maximum value and an average value or between a mean value and a minimum value, whether the control rods in the group/subgroup has fault phenomena such as synchronism loss, rod clamping or the like is determined.

Description

A kind of control rod step-out monitoring method
Technical field
The invention belongs to a kind of pressurized-water reactor nuclear power plant control method, be specifically related to a kind of pressurized water reactor nuclear power station control bar step-out monitoring method.
Background technology
The pressurized-water reactor nuclear power plant of different capacity grade, have quantity different, for pile neutron absorb C&P systems, as 600,000 multikilowatt pressurized-water reactor nuclear power plants have 33 control rods, and kilowatt pressurized water reactor nuclear power station has 61 control rods, AP1000 nuclear power station has 69 control rods, and EPR1000 has 89 control rods.Control rod be pile reactivity control the most directly, the most fast, regulating measure the most flexibly.
The control that control rod runs is by Special instrument Ore-controlling Role---Rod control and position indication system forms.Rod control and position indication system comprises rod control system and excellent position system two parts.
Rod control system is used for for control rod drive mechanisms (CRD) (CRDM) coil power supply, make two of CRDM inside hooks replace adhesive, open, move, thus drive the control rod that hangs on CRDM driving stem to rise in reactor core active region, lower slotting and keep motionless, it is made to rest on diverse location in reactor core, to absorb number of neutrons in various degree, thus regulate the reactivity of reactor, and then regulate the output power of reactor.Rod control system produces the given excellent position of control rod movement according to the control command received, and also cries instruction rod position, requires excellent position, for expressing the position that control rod needs to arrive.Given excellent position is that control rod runs the key parameter controlled, and be also the important parameter that reactor safety calculates and monitors, its resolution is 1 step.
The operation of control rod in reactor core is mainly divided into control rod group or subgroup controls, control rod in a control rod group or subgroup is arranged symmetrically with in reactor core the control rod of reactor core center (be positioned at except), control rod rod group/subgroup is the elementary cell that reactor controls, and simultaneously general or difference partly walks operation.
Rod position system is used for coming the position of Monitoring and Controlling rod in reactor core by stick location probe, utilizes electromagnetic induction principle to produce the measuring stick position of control rod.Measuring stick position, also referred to as the excellent position of actual measurement, is exactly that its resolution is general lower, such as 6 steps, 8 steps etc. for the actual position arrived of Monitoring and Controlling rod.
Control rod step-out just refers to that the control rod in control rod group/subgroup of simultaneously running occurs that position is inconsistent, control rod rod position inconsistent, namely control rod step-out is accumulated to a certain degree, reactor core neutron flux will be caused to distort, thus affect the control of pile reactivity and the safety of reactor.Timeliness coverage control rod step-out can be related to cluster inserts spacing realization degree, power distribution calculates validity and find the promptness of driving mechanism fault (sliding steps, card rod etc.) and electrical equipment malfunction.Therefore, the monitoring of control rod step-out is of great significance for the control of reactor and safe tool.
Two kinds are mainly comprised: the monitoring of " rod/group " step-out and " rod/rod " step-out monitoring in the step-out monitoring of current control rod.
The monitoring of " rod/group " step-out refers to the monitoring inconsistent to the given position of the measuring stick position of each control rod in control rod rod group/subgroup and excellent group/subgroup; The monitoring of " rod/group " step-out is by being divided into static step-out and motion step-out.
The monitoring that measuring stick position between the monitoring of s " rod/rod " step-out refers to each control rod in control rod rod group/subgroup is inconsistent.
Above-mentioned step-out monitoring measure and method; can well Monitoring and Controlling rod step-out, card rod etc. phenomenon of the failure; but existing defects: the threshold value of monitoring due to these step-outs is comparatively large (if " rod/group " step-out monitoring threshold is 8 steps or 12 steps; " rod/rod " step-out monitoring threshold is 9 steps); monitoring accuracy is lower; often could monitor out when control rod step-out is accumulated to many; therefore step-out and the card rod of Timeliness coverage control rod is unfavorable for; be unfavorable for protecting driving mechanism, be also unfavorable for the safety of reactor.
Complete the accurate location of control rod, need the deviation between the given excellent position of Monitor and Control rod and measuring stick position; But not high because of control rod positional accuracy measurement, rod position measurement Channel Response Time is longer, and the threshold value of step-out monitoring is comparatively large, so it is inadequate for only arranging the monitoring of " rod/group " step-out with " rod/rod " step-out monitoring.
Summary of the invention
The object of this invention is to provide a kind of control rod step-out monitoring method, when not increasing new monitoring parameter, reducing the threshold value of control rod step-out monitoring, improve the precision of step-out monitoring, the step-out of control rod can be found more in time, as early as possible.
The present invention is achieved in that a kind of control rod step-out monitoring method, and it comprises the steps,
(1) judge whether control rod operates other step-out and report to the police, if do not had, just enters next step;
(2) judge that in subgroup/group, all control rods are all in same position, if so, are then for further processing, otherwise, wait for that all control rods are in same position;
(3) whether the position of monitoring the first bundle control rod changes, and if so, is recording its current location;
(4) whether the position of monitoring the second bundle control rod changes, and if so, is recording its current location;
(5) whether the position monitoring last bundle control rod successively changes, and if so, is recording its current location;
(6) after the position of control rods all in subgroup/group all changes, the maximal value of these record positions, minimum value and mean value is calculated;
(7) maximal value and the difference of mean value and the difference of mean value and minimum value is calculated;
(8) above-mentioned calculated difference exceedes predetermined alarm threshold value, then trigger limit average step-out and report to the police, otherwise enters and circulate next time.
Advantage of the present invention is, by the given excellent position situation of change when measuring stick position of control rod changes in Monitoring and Controlling rod group/subgroup, and finds out its maximal value, minimum value and mean value; By analyzing maximal value and mean value or the deviation between mean value and minimum value or absolute value of the bias, thus determine whether the control rod in group/subgroup exists the phenomenon of the failure such as step-out or card rod; It is not controlled the impact of response time of excellent translational speed, rod position measurement passage, and therefore the precision of control rod step-out monitoring is high; Its step-out monitoring threshold little (as 4 steps or less), is conducive to the step-out phenomenon of Timeliness coverage control rod, is more conducive to the safety protecting nuclear power plant.
Accompanying drawing explanation
Fig. 1 is a kind of control rod step-out monitoring method process flow diagram provided by the present invention.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
In the control procedure of reactor control rod, control rod is all divided into several groups (in the nuclear power plant had according to its effect, group also can be divided into subgroup), control rod in group/subgroup is arranged symmetrically with in reactor core, and synchronous operation all simultaneously in control, there is identical instruction rod position, i.e. given excellent position.Therefore, theoretically, the measuring stick position of all control rods in group/subgroup changes simultaneously, has consistance.
In fact, because the factor such as electric parameter of the resolution of stick location probe and manufacturing accuracy, rod position measurement passage there are differences, in group/subgroup, the measuring stick position change of every root control rod is not quite identical, there is deviation.
This step-out monitoring method is exactly the deviation by every root control rod measuring stick position change in monitoring group/subgroup, realizes control rod step-out and the timely monitoring and the warning that block rod.
In control rod motion process, in monitoring group, the change of the measuring stick position of each root control rod, when its measuring stick position changes, records corresponding given excellent position; When the measuring stick position of control rods all in group/subgroup all changes, by computing, find out its maximal value, minimum value and mean value.By monitoring and analyze the deviation between these values, thus determine whether the control rod in group/subgroup exists the phenomenon of the failure such as step-out or card rod.
A kind of control rod step-out monitoring method, it comprises the steps:
(1) judge whether control rod operates other step-out and report to the police, if do not had, just enters next step;
(2) judge that in subgroup/group, all control rods are all in same position, if so, are then for further processing, otherwise, wait for that all control rods are in same position;
(3) whether the position of monitoring the first bundle control rod changes, and if so, is recording its current location;
(4) whether the position of monitoring the second bundle control rod changes, and if so, is recording its current location;
(5) whether the position monitoring last bundle control rod successively changes, and if so, is recording its current location;
(6) after the position of control rods all in subgroup/group all changes, the maximal value of these record positions, minimum value and mean value is calculated;
(7) maximal value and the difference of mean value and the difference of mean value and minimum value is calculated;
(8) above-mentioned calculated difference exceedes predetermined alarm threshold value, then trigger limit average step-out and report to the police, otherwise enters and circulate next time.
The present invention by the given excellent position when measuring stick position of each control rod changes in Monitoring and Controlling rod group, then calculates average and extreme value, then calculates deviation, reports to the police with regard to triggering step-out if deviation exceeds threshold value.In the present invention, threshold value ratio " rod/group " the step-out monitoring of step-out monitoring is little with the threshold value of " rod/rod " step-out monitoring, and such as 4 steps are even less.

Claims (1)

1. a control rod step-out monitoring method, is characterized in that: it comprises the steps,
(1) judge whether control rod operates other step-out and report to the police, if do not had, just enters next step;
(2) judge that in subgroup/group, all control rods are all in same position, if so, are then for further processing, otherwise, wait for that all control rods are in same position;
(3) whether the position of monitoring the first bundle control rod changes, and if so, is recording its current location;
(4) whether the position of monitoring the second bundle control rod changes, and if so, is recording its current location;
(5) whether the position monitoring last bundle control rod successively changes, and if so, is recording its current location;
(6) after the position of control rods all in subgroup/group all changes, the maximal value of these record positions, minimum value and mean value is calculated;
(7) maximal value and the difference of mean value and the difference of mean value and minimum value is calculated;
(8) above-mentioned calculated difference exceedes predetermined alarm threshold value, then trigger limit average step-out and report to the police, otherwise enters and circulate next time.
CN201310306959.3A 2013-07-22 2013-07-22 Monitoring method for synchronism loss of control rods Pending CN104332200A (en)

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112185596A (en) * 2020-09-30 2021-01-05 中国核动力研究设计院 Rod falling time measuring method, medium and system based on nuclear power station measuring coil
CN112599264A (en) * 2020-12-05 2021-04-02 核电运行研究(上海)有限公司 Method for accurately positioning position of control rod

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JPH04336607A (en) * 1991-05-14 1992-11-24 Toshiba Corp Diagnosing device for control of position detecting part
CN1283302A (en) * 1997-12-23 2001-02-07 Abb燃烧工程核力公司 Method for detecting abnormal generation of core control element position signal
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JP2011208960A (en) * 2010-03-29 2011-10-20 Hitachi-Ge Nuclear Energy Ltd Method for monitoring withdrawal of control rod
US20130177123A1 (en) * 2008-01-09 2013-07-11 Analysis And Measurement Services Corporation Control Rod Position Indication Systems and Methods for Nuclear Power Plants

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Publication number Priority date Publication date Assignee Title
CN1038896A (en) * 1988-06-08 1990-01-17 法玛通有限公司 Survey the control cluster and drop to the interior method and apparatus of nuclear reactor
JPH04336607A (en) * 1991-05-14 1992-11-24 Toshiba Corp Diagnosing device for control of position detecting part
CN1283302A (en) * 1997-12-23 2001-02-07 Abb燃烧工程核力公司 Method for detecting abnormal generation of core control element position signal
KR100655055B1 (en) * 2005-12-16 2006-12-06 두산중공업 주식회사 Method of verificating location of a control element in the reactor core protection system
US20130177123A1 (en) * 2008-01-09 2013-07-11 Analysis And Measurement Services Corporation Control Rod Position Indication Systems and Methods for Nuclear Power Plants
CN101840737A (en) * 2009-09-02 2010-09-22 中广核工程有限公司 Digital rod position control system and method
JP2011208960A (en) * 2010-03-29 2011-10-20 Hitachi-Ge Nuclear Energy Ltd Method for monitoring withdrawal of control rod

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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112185596A (en) * 2020-09-30 2021-01-05 中国核动力研究设计院 Rod falling time measuring method, medium and system based on nuclear power station measuring coil
CN112185596B (en) * 2020-09-30 2022-02-11 中国核动力研究设计院 Rod falling time measuring method, medium and system based on nuclear power station measuring coil
CN112599264A (en) * 2020-12-05 2021-04-02 核电运行研究(上海)有限公司 Method for accurately positioning position of control rod
CN112599264B (en) * 2020-12-05 2023-02-14 核电运行研究(上海)有限公司 Method for accurately positioning position of control rod

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