CN202948734U - Reactor automatic track while scanning (ATWS) accident response system - Google Patents
Reactor automatic track while scanning (ATWS) accident response system Download PDFInfo
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- CN202948734U CN202948734U CN2012205491824U CN201220549182U CN202948734U CN 202948734 U CN202948734 U CN 202948734U CN 2012205491824 U CN2012205491824 U CN 2012205491824U CN 201220549182 U CN201220549182 U CN 201220549182U CN 202948734 U CN202948734 U CN 202948734U
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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 utility model relates to the technical field of nuclear power and in particular discloses a reactor ATWS accident response system. The system comprises a plurality of pipelines which are redundant with each other, wherein each pipeline comprises a concentrated boron box which is arranged in a nuclear auxiliary plant; the upper end pipeline of the concentrated boron box is connected with a safety valve, the bottom of the concentrated boron box is connected with a reciprocating pump through a pipeline, and the pipelines at which the reciprocating pump and the safety valve are positioned are gathered to a main pipeline; an electric ball valve A is arranged on the main pipeline; the main pipeline stretches into a safety shell; a check valve and an electric ball valve C are arranged on the main pipeline which stretches into the safety shell; and an electric ball valve B is arranged between the upper end of the concentrated boron box and the main pipeline. When an ATWS accident occurs, the system automatically starts related valves on a boron injection pump and an injection pipeline, a boric acid solution is injected into the reactor core, the reactor is positioned in a subcritical state, the reactor core safety is guaranteed, and the safety of the reactor is improved.
Description
Technical field
The utility model belongs to the nuclear power technology field, is specifically related to a kind of ATWS accident answering system.
Background technology
Two traditional generations or two generations+nuclear power are failed ATWS(the emergency shut-down anticipated transient usually) accident is as super design reference, use the existing system configuration, by operator, coherent signal and information are carried out artificial judgment, the relevant system of manual operation and valve inject reactor core with BAS.When the ATWS accident occurs, if can not in time BAS be injected reactor core, can not guarantee reactor core safety.Must make reactor for subcritical state, the security of guarantee reactor.Due to manually-operated, make the ability of reply accident be subject to various interference and impact simultaneously, traditional accident treatment maloperation probability is higher.
Summary of the invention
The purpose of this utility model is to provide a kind of security that can further improve reactor, reduces the integrated small heap ATWS accident answering system of damage sequence and frequency.
Realize that the technical solution of the utility model is as follows:
Reactor ATWS accident answering system, it comprises some pipelines of redundancy each other, every pipeline comprises the dense boron case that is arranged in nuclear auxiliary building, B solution is equipped with in dense boron case inside, the upper end pipeline connection safety valve of described dense boron case, the bottom of dense boron case is connected by pipeline with reciprocating pump, and the pipeline at reciprocating pump and safety valve place converges on main line; Described main line is provided with electrical ball valve A; Described main line extends in containment, and the main line that extends in containment is provided with non-return valve and electrical ball valve C; Be provided with electrical ball valve B between the upper end of described dense boron case and main line.
In above-mentioned reactor ATWS accident answering system: be provided with tensimeter between the upper end of described dense boron case and electrical ball valve B.
In above-mentioned reactor ATWS accident answering system: be provided with flowmeter on the main line in nuclear auxiliary building.
In above-mentioned reactor ATWS accident answering system: be provided with non-return valve on the main line in described containment.
The obtained beneficial effect of the utility model is as follows: when the ATWS accident occurs, native system is according to corresponding signal, automatically start the related valve of annotating on boron pump and injection pipeline, BAS is injected reactor core, guarantee that reactor is in subcritical state, guarantee reactor core safety, improve the security of reactor.Adopt this system, can reduce because using system or equipment, making it reply accident ability is interfered or affects, tackle the ability of this type of accident with further raising nuclear power plant, reduction personnel maloperation probability, the consequence that reduces accident frequency and bring, raising and the improvement of the security of final realization response heap.
Description of drawings
Fig. 1 is reactor ATWS accident answering system schematic diagram;
In figure: 1. dense boron case; 2. reciprocating pump; 3. tensimeter; 4. flowmeter; 5. electrical ball valve A; 6. electrical ball valve B; 7. non-return valve; 8. electrical ball valve C; 9. safety valve.
Embodiment
Below in conjunction with the drawings and specific embodiments, the present invention is described in detail.
As shown in Figure 1, the ATWS accident answering system in the present embodiment comprises two circuits of redundancy each other, and every circuit is all across in nuclear auxiliary building and containment.
The structure of each pipeline is as follows:
Dense boron case 1 is installed in nuclear auxiliary building, and there is B solution its inside, and the upper end of dense boron case 1 is by safety valve 9 pilot piping foldings, and the bottom of dense boron case 1 is connected with reciprocating pump 2, and the pipeline at reciprocating pump 2 and safety valve 9 places converges on main line.The upper end of dense boron case 1 is connected with tensimeter 3 and electrical ball valve B6, and the main line in nuclear auxiliary building also is equipped with electrical ball valve A5 and flowmeter 4, and wherein electrical ball valve A5 receives the reactor protection signal and starts.
Main line extends in containment, and on pipeline, non-return valve 7 and electrical ball valve C8 is installed, and wherein electrical ball valve C8 receives the guard signal of reactor and starts.Main line in containment one directly into reactor.
in when, the ATWS accident occuring and following corresponding reactor protection signal when, the electrical ball valve A5 that start one or two reciprocating pump 2 and injection pipeline on automatic according to signal, electrical ball valve B6 and electrical ball valve C8, start simultaneously non-return valve 7 and safety valve 9, with the BAS of preparing in advance in dense boron case 1, with certain injection rate piii reactor reactor core, in the process of B Implanted acid solution, operator can observe by tensimeter 3 and flowmeter 4 pressure of voltage stabilizer, the temperature indication of water level and reactor coolant, stop in good time or again start reciprocating pump 2, the volumetric contraction of bringing because of decrease temperature and pressure with intermitten service mode compensatory reactionBu Changfanying reactor coolant system, when the liquid level of dense boron case 1 arrives low-flow water level, automatically send warning, and stop the operation of reciprocating pump 2.At last, the BAS of injection can provide certain shutdown margin for reactor core, guarantees that reactor is in subcritical state, namely reaches the needed boron concentration requirement of cold shut state.
Obviously, those skilled in the art can carry out various changes and modification and not break away from spirit and scope of the present utility model the utility model.If these are revised and within modification belongs to the scope of the utility model claim and equivalent technologies thereof, the utility model also is intended to comprise these changes and modification interior.
Claims (3)
1. reactor ATWS accident answering system, it comprises some pipelines of redundancy each other, and every pipeline comprises the dense boron case (1) that is arranged in nuclear auxiliary building, and B solution is equipped with in inside, it is characterized in that: also comprise reciprocating pump (2) and electrical ball valve; The upper end pipeline connection safety valve (9) of described dense boron case (1), the bottom of dense boron case (1) is connected by pipeline with reciprocating pump (2), and the pipeline at reciprocating pump (2) and safety valve (9) place converges on main line; Described main line is provided with electrical ball valve A(5); Described main line extends in containment, and the main line that extends in containment is provided with non-return valve (7) and electrical ball valve C(8); Be provided with electrical ball valve B(6 between the upper end of described dense boron case (1) and main line).
2. reactor ATWS accident answering system as claimed in claim 1, is characterized in that: the upper end of described dense boron case (1) and electrical ball valve B(6) between be provided with tensimeter (3).
3. reactor ATWS accident answering system as claimed in claim 1 is characterized in that: the main line in nuclear auxiliary building is provided with flowmeter (4).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012205491824U CN202948734U (en) | 2012-10-25 | 2012-10-25 | Reactor automatic track while scanning (ATWS) accident response system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012205491824U CN202948734U (en) | 2012-10-25 | 2012-10-25 | Reactor automatic track while scanning (ATWS) accident response system |
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| Publication Number | Publication Date |
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| CN202948734U true CN202948734U (en) | 2013-05-22 |
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| CN2012205491824U Expired - Lifetime CN202948734U (en) | 2012-10-25 | 2012-10-25 | Reactor automatic track while scanning (ATWS) accident response system |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103985421A (en) * | 2014-05-06 | 2014-08-13 | 中科华核电技术研究院有限公司 | Method for improving security of nuclear power unit during failure of emergency shut-down of reactor |
| CN104332188A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Method for alleviating primary loop overpressure during normal feedwater fail-ATWS (Anticipated Transients Without Scram) accident |
| CN106887259A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | A kind of nuclear power plant fast and safely reactor shut-off system |
| CN109215813A (en) * | 2018-09-13 | 2019-01-15 | 中国核动力研究设计院 | Pressurized-water reactor thimble tube complementary shutdown system and method |
| CN109473185A (en) * | 2018-11-13 | 2019-03-15 | 中国核动力研究设计院 | A kind of test device and its test method of robotics reactor shut-off system |
| CN111540485A (en) * | 2020-05-18 | 2020-08-14 | 中国核动力研究设计院 | Protection system for dealing with ATWS (automatic water supply) accident of nuclear power plant caused by loss of normal water supply |
-
2012
- 2012-10-25 CN CN2012205491824U patent/CN202948734U/en not_active Expired - Lifetime
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104332188A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Method for alleviating primary loop overpressure during normal feedwater fail-ATWS (Anticipated Transients Without Scram) accident |
| CN103985421A (en) * | 2014-05-06 | 2014-08-13 | 中科华核电技术研究院有限公司 | Method for improving security of nuclear power unit during failure of emergency shut-down of reactor |
| CN103985421B (en) * | 2014-05-06 | 2016-09-28 | 中广核研究院有限公司 | The method that reactor fails to improve nuclear power generating sets safety during emergency shut-down |
| CN106887259A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | A kind of nuclear power plant fast and safely reactor shut-off system |
| CN109215813A (en) * | 2018-09-13 | 2019-01-15 | 中国核动力研究设计院 | Pressurized-water reactor thimble tube complementary shutdown system and method |
| CN109473185A (en) * | 2018-11-13 | 2019-03-15 | 中国核动力研究设计院 | A kind of test device and its test method of robotics reactor shut-off system |
| CN109473185B (en) * | 2018-11-13 | 2022-07-29 | 中国核动力研究设计院 | Testing device and testing method for automatic chemical reactor shutdown system |
| CN111540485A (en) * | 2020-05-18 | 2020-08-14 | 中国核动力研究设计院 | Protection system for dealing with ATWS (automatic water supply) accident of nuclear power plant caused by loss of normal water supply |
| CN111540485B (en) * | 2020-05-18 | 2022-02-01 | 中国核动力研究设计院 | Protection system for dealing with ATWS (automatic water supply) accident of nuclear power plant caused by loss of normal water supply |
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| C14 | Grant of patent or utility model | ||
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Granted publication date: 20130522 |
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| CX01 | Expiry of patent term |