CN102306508A - Reactivity instrument for critical monitoring and critical extrapolation of reactor - Google Patents
Reactivity instrument for critical monitoring and critical extrapolation of reactor Download PDFInfo
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- CN102306508A CN102306508A CN201110263094A CN201110263094A CN102306508A CN 102306508 A CN102306508 A CN 102306508A CN 201110263094 A CN201110263094 A CN 201110263094A CN 201110263094 A CN201110263094 A CN 201110263094A CN 102306508 A CN102306508 A CN 102306508A
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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
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- 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 belongs to a measurement device of a nuclear reactor and in particular relates to a device for measuring the reactivity of a nuclear reactor and monitoring the critical state of the nuclear reactor. The device is composed of a data processor and a signal conditioner; an isolation amplifier is arranged in the signal conditioner; and the input end of the isolation amplifier is provided with a P2 signal input port. The device not only has the function of measuring the reactivity but also has the critical monitoring and critical extrapolation functions, and can automatically measure the reactivity of the reactor and perform the offline processing on the measurement result; and when the critical extrapolation and the critical monitoring are conducted, the selection of extrapolation sub-function items and the selection of extrapolation data intervals can be carried out via a human-machine interface, diversified display and record can be carried out on the result. The reactivity instrument has the advantages of high automation degree, rapid measurement speed, high measurement accuracy and simplicity and convenience in operation, thereby greatly improving the functionality and use ratio of the device and achieving the full coverage of the full-function application field before the nuclear reactor is in a critical state.
Description
Technical field
The invention belongs to a kind of measurement mechanism of nuclear reactor, be specifically related to measure the device of nuclear reactor reactivity and supervision nuclear reactor critical conditions.
Background technology
The critical point of reactor is the very important parameter of a relevant reactor safety; Know that in advance its critical point is absolutely necessary to reactor operation, the critical supervision of reactor is to judging that reactor reaches initial critical stage and whether is in a safe condition and plays important effect during the loading and unloading material.
It is also to lean on the operator manually to extrapolate to calculate fully through specialized equipment collection correlation parameter to realize basically that reactor current reaches critical outer critical supervision of spreading in the loading and unloading material process.Its defective is: because that extrapolation is calculated is comparatively complicated, the manual type spended time is long and very easily make mistakes; Tradition reactivity meter neutron fluence rate signal derives from the current signal of power district or mesozone, owing to receive the restriction of detector sensitivity, and at critical extrapolation phase detection device output current about 10
-10A-10
-9A, so faint pickup electrode is subject to external interference, measures accuracy and is difficult to guarantee; The neutron fluence rate data of obtaining when utilizing traditional reactivity meter to measure reactivity are carried out critical extrapolation, and choosing of data segment is difficult to accomplish preferably.
Point out according to external existing research: reactivity meter not only can be used for traditional reactive monitoring, can also be when critical approaching, as the monitoring tool of subcriticality.Like " Journal of NUCLEAR SCIENCE and TECHNOLOGY " Vol. 42; No. 2; P. " Subcriticality Measurement of Pressurized Water Reactors during Criticality Approach using a Digital Reactivity Meter " among 145 – 152 (February 2005); Proposed when reactor control rod is regulated, to utilize reactive variation tendency calculate critical moment-modification method of kind of method and correlation parameter; And provided and utilize reactivity meter on presurized water reactor, to realize the feasibility that subcriticality is measured; But this article has only provided a kind of possibility in theory, does not also see that reactivity meter really is used for the relevant report that subcriticality is measured at present.Therefore, it is reactive to develop a kind of both energy measurements, and the specialized equipment that can carry out subcritical supervision again is very necessary.
Summary of the invention
The object of the present invention is to provide a kind of reactivity meter that can be used for critical supervision of reactor and critical extrapolation.This reactivity meter not only can be measured reactivity, can also realization response pile critical supervision and critical extrapolation, realizes the comprehensive covering to the critical preceding global function application of reactor.
Technical scheme of the present invention is following:
Can be used for the reactivity meter of critical supervision of reactor and critical extrapolation, comprise data processor and signal conditioner; Data processor is made up of portable computer and data processor interface circuit board, and the data processor interface circuit board is inserted in the portable computer, and portable computer has data processor printer interface and data processor data-interface; Data processor links to each other through data line with the signal conditioner data-interface through the data processor data-interface with signal conditioner; Signal conditioner is made up of cabinet and printed circuit board (PCB); Printed circuit board (PCB) is arranged in the cabinet; Mesozone voltage amplifier, power district voltage amplifier, I/V transducer, A/D change-over circuit, two utmost point amplifiers and signal conditioner interface circuit are welded on printed circuit board (PCB); The input end of voltage amplifier and power district voltage amplifier is respectively equipped with neutron fluence rate voltage signal input port in the mesozone; Input end at the I/V transducer is provided with neutron fluence rate electric current input port; Output terminal at the signal conditioner interface circuit is provided with reactive voltage signal delivery outlet and reactor capability voltage signal delivery outlet; Low-tension supply is arranged in the cabinet, links to each other with printed circuit board (PCB) through lead; The signal conditioner data-interface is arranged on the cabinet, links to each other with printed circuit board (PCB) through lead,
It is characterized in that:Also be provided with isolated amplifier in the signal conditioner of said reactivity meter, be provided with the P2 signal input at the input end of isolated amplifier; Isolated amplifier links to each other with the signal conditioner interface circuit through data line; The P2 signal input links to each other with printed circuit board (PCB) through lead.
Its supplementary features are:
The said P2 signal input that is arranged on the isolated amplifier input end has a plurality of, links to each other with printed circuit board (PCB) through lead.
Described P2 signal input has 24, links to each other with printed circuit board (PCB) through lead.
Effect of the present invention is: because the signal conditioner of reactivity meter of the present invention has increased isolated amplifier; Import through the P2 signal; Complex reaction property measurement processing software, subcritical supervisor software and off-line data process software; Make the robotization of extrapolation computed altitude, expanded application function greatly, make reactivity meter realize comprehensive covering first the critical preceding global function application of reactor; The present invention will be relevant with reactor safety the measuring task or the supervisory role of other parameters be integrated in same the equipment, greatly improved the functional integration and the utilization factor of equipment; The present invention is easy and simple to handle; But the interval critical extrapolation of different pieces of information is calculated and critical supervision computation requirement in the same time period of Rapid Realization; Guaranteed the precision that extrapolation is calculated and critical supervision is calculated; Equipment can intuitively show data with numerical value or curve mode after calculating completion, compares with the manual type of comparing legacy equipment, can improve efficiency of measurement more than 90%.
Description of drawings
Fig. 1 is a structural representation of the present invention.
Among the figure: 1. data processor; 2. portable computer; 3. data processor interface circuit board;
4. data processor printer interface; 5. data processor data-interface; 6. signal conditioner; 7. cabinet; 8. printed circuit board (PCB); 9. isolated amplifier; 10.P2 signal input; 11. mesozone voltage amplifier;
12. neutron fluence rate voltage signal input port; 13. power district voltage amplifier; 14. neutron fluence rate electric current input port; 15. I/V transducer; 16.A/D change-over circuit; 17. two utmost point amplifiers; 18. low-tension supply; 19. reactive voltage signal delivery outlet; 20. reactor capability voltage signal delivery outlet; 21. signal conditioner interface circuit; 22. signal conditioner data-interface.
Embodiment
As shown in Figure 1, reactivity meter of the present invention comprises two parts: data processor 1 and signal conditioner 6.Data processor 1 and signal conditioner 6 link to each other through data line.
Principle of work of the present invention is following:
1. reactivity measurement
During reactivity measurement, according to the difference of reactor power level, the neutron signal of being exported by corresponding detector is input in the reactivity meter of the present invention after the electronic circuit processing and amplifying.The neutron fluence rate signal is input to signal conditioner 6 through neutron fluence rate voltage signal input port 12 and neutron fluence rate electric current input port 14, sends into A/D converter 16 through conversion and amplifying signal, after the A/D conversion, delivers to signal conditioner interface circuit 21; 8～24 road relevant P2 signals are sent into isolated amplifier 9 through P2 signal input 10; The signal of isolating after amplifying is delivered to signal conditioner data interface circuit 21; Signal conditioner data interface circuit 21 is sent into the portable computer 2 in the data processor 1 with the data-signal that obtains through data line; Portable computer 2 complex reaction property measurement processing softwares and off-line data process software write down and handle the data that obtain; Calculate reactivity, show power and reactive value and power and responsiveness curve in real time.After measuring end, access the processed offline that record data carry out the reactivity measurement result through portable computer 2.
2. reaching critical extrapolation measures
When reaching critical extrapolation and measuring; Relevant P2 signal (source region neutron fluence rate signal, mesozone neutron fluence rate signal, control rod rod position signal) is sent into isolated amplifier 9 through the P2 signal input 10 of appointment arbitrarily; The signal of isolating after amplifying is delivered to signal conditioner data interface circuit 21; Signal conditioner data interface circuit 21 is sent into the portable computer 2 in the data processor 1 with the data-signal that obtains through data line, portable computer 2 cooperate subcritical supervisor software and off-line data process software to the data of acquisition write down, processing and screen display.The operator operates according to screen prompt, and critical extrapolated value and critical extrapolated curve are handled and provided to computing machine according to operator's input to the data that obtain.
3. the critical supervision of loading and unloading material
During the critical supervision of loading and unloading material; Relevant P2 signal (source region neutron fluence rate signal) is sent into isolated amplifier 9 through the P2 signal input 10 of appointment; The signal of isolating after amplifying is delivered to signal conditioner data interface circuit 15; Signal conditioner data interface circuit 21 is sent into the portable computer 2 in the data processor 1 with the data-signal that obtains through data line, portable computer 2 cooperate subcritical supervisor software and off-line data process software to the data of acquisition write down, processing and screen display.The operator loads and unloads the preface operation of material step according to screen prompt, and computing machine is handled the data that obtain, and provides the critical supervision curve corresponding to critical supervision value and loading and unloading material process.
When critical extrapolation and critical supervision, can through man-machine interface respectively extrapolate the subfunction item selection and the extrapolation data interval selection.
Claims (3)
1. the reactivity meter that can be used for critical supervision of reactor and critical extrapolation comprises data processor (1) and signal conditioner (6); Data processor (1) is made up of portable computer (2) and data processor interface circuit board (3); Data processor interface circuit board (3) is inserted in the portable computer (2), and portable computer (2) has data processor printer interface (4) and data processor data-interface (5); Data processor (1) links to each other through data line with signal conditioner data-interface (22) through data processor data-interface (5) with signal conditioner (6); Signal conditioner (6) is made up of cabinet (7) and printed circuit board (PCB) (8); Printed circuit board (PCB) (8) is arranged in the cabinet (7); Mesozone voltage amplifier (11), power district voltage amplifier (13), I/V transducer (15), A/D change-over circuit (16), two utmost point amplifiers (17) and signal conditioner interface circuit (21) are welded on printed circuit board (PCB) (8); The input end of voltage amplifier in the mesozone (11) and power district voltage amplifier (13) is respectively equipped with neutron fluence rate voltage signal input port (12); Input end at I/V transducer (15) is provided with neutron fluence rate electric current input port (14); Output terminal at signal conditioner interface circuit (21) is provided with reactive voltage signal delivery outlet (19) and reactor capability voltage signal delivery outlet (20); Low-tension supply (18) is arranged in the cabinet (7), links to each other with printed circuit board (PCB) (8) through lead; Signal conditioner data-interface (22) is arranged on the cabinet (7); Link to each other with printed circuit board (PCB) (8) through lead; It is characterized in that: also be provided with isolated amplifier (9) in the signal conditioner of said reactivity meter (6), be provided with P2 signal input (10) at the input end of isolated amplifier (9); Isolated amplifier (9) links to each other with signal conditioner interface circuit (21) through data line; P2 signal input (10) links to each other with printed circuit board (PCB) (8) through lead.
2. according to the described reactivity meter that can be used for critical supervision of reactor and critical extrapolation of claim 1; It is characterized in that: the said P2 signal input (10) that is arranged on isolated amplifier (9) input end has a plurality of, links to each other with printed circuit board (PCB) (8) through lead.
3. according to claim 1 or the 2 described reactivity meters that can be used for critical supervision of reactor and critical extrapolation, it is characterized in that: described P2 signal input (10) has 24, links to each other with printed circuit board (PCB) (8) through lead.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201110263094.8A CN102306508B (en) | 2011-09-07 | 2011-09-07 | Reactivity instrument for critical monitoring and critical extrapolation of reactor |
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| CN201110263094.8A CN102306508B (en) | 2011-09-07 | 2011-09-07 | Reactivity instrument for critical monitoring and critical extrapolation of reactor |
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| CN102306508A true CN102306508A (en) | 2012-01-04 |
| CN102306508B CN102306508B (en) | 2014-04-23 |
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Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103514967A (en) * | 2012-06-15 | 2014-01-15 | 北京凯佰特科技有限公司 | Intelligent reactor control method |
| CN104376884A (en) * | 2013-08-15 | 2015-02-25 | 中国原子能科学研究院 | Portable reactivity meter for carrying out full measuring range automatic monitoring on reactor signal, and reactivity correction method |
| CN104409120A (en) * | 2014-12-11 | 2015-03-11 | 中国核动力研究设计院 | Switching method for current linear amplification automatic range |
| CN105788666A (en) * | 2014-12-23 | 2016-07-20 | 福建福清核电有限公司 | Nuclear reactor critical process control method |
| CN107221365A (en) * | 2017-06-26 | 2017-09-29 | 中广核研究院有限公司 | A kind of commercial presurized water reactor physical test system |
| 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 |
| CN109961861A (en) * | 2017-12-14 | 2019-07-02 | 中国核动力研究设计院 | Reactivity measurement instrument under a kind of nuclear power plant reactor depth subcritical state |
| CN112488461A (en) * | 2020-11-13 | 2021-03-12 | 中国辐射防护研究院 | Method for estimating total fission times in emergency of metal uranium critical accident |
| CN112488465A (en) * | 2020-11-13 | 2021-03-12 | 中国辐射防护研究院 | Method for estimating total fission times of triuranium octoxide in critical accident emergency |
| CN112488460A (en) * | 2020-11-13 | 2021-03-12 | 中国辐射防护研究院 | Method for estimating total fission times of uranium dioxide in emergency of critical accident |
| 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 |
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Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103514967B (en) * | 2012-06-15 | 2016-03-02 | 北京凯佰特科技有限公司 | Intelligent response heap control method |
| CN103514967A (en) * | 2012-06-15 | 2014-01-15 | 北京凯佰特科技有限公司 | Intelligent reactor control method |
| CN104376884A (en) * | 2013-08-15 | 2015-02-25 | 中国原子能科学研究院 | Portable reactivity meter for carrying out full measuring range automatic monitoring on reactor signal, and reactivity correction method |
| CN104409120A (en) * | 2014-12-11 | 2015-03-11 | 中国核动力研究设计院 | Switching method for current linear amplification automatic range |
| CN105788666A (en) * | 2014-12-23 | 2016-07-20 | 福建福清核电有限公司 | Nuclear reactor critical process control method |
| CN107221365A (en) * | 2017-06-26 | 2017-09-29 | 中广核研究院有限公司 | A kind of commercial presurized water reactor physical test system |
| CN109961861A (en) * | 2017-12-14 | 2019-07-02 | 中国核动力研究设计院 | Reactivity measurement instrument under a kind of nuclear power plant reactor depth subcritical state |
| CN109256226B (en) * | 2018-11-05 | 2020-07-03 | 三门核电有限公司 | Reactor critical extrapolation monitoring system and method |
| 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 |
| CN112488461A (en) * | 2020-11-13 | 2021-03-12 | 中国辐射防护研究院 | Method for estimating total fission times in emergency of metal uranium critical accident |
| CN112488465A (en) * | 2020-11-13 | 2021-03-12 | 中国辐射防护研究院 | Method for estimating total fission times of triuranium octoxide in critical accident emergency |
| CN112488460A (en) * | 2020-11-13 | 2021-03-12 | 中国辐射防护研究院 | Method for estimating total fission times of uranium dioxide in emergency of critical accident |
| CN112488460B (en) * | 2020-11-13 | 2022-11-15 | 中国辐射防护研究院 | Method for estimating total fission times of uranium dioxide in emergency of critical accident |
| CN112488465B (en) * | 2020-11-13 | 2022-11-18 | 中国辐射防护研究院 | Method for estimating total fission times of triuranium octoxide in critical accident emergency |
| CN112488461B (en) * | 2020-11-13 | 2022-11-18 | 中国辐射防护研究院 | Method for estimating total fission times in emergency of metal uranium critical accident |
| 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 |
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| CN102306508B (en) | 2014-04-23 |
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