CN101847451A - Safety injection system - Google Patents
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- CN101847451A CN101847451A CN200910108230A CN200910108230A CN101847451A CN 101847451 A CN101847451 A CN 101847451A CN 200910108230 A CN200910108230 A CN 200910108230A CN 200910108230 A CN200910108230 A CN 200910108230A CN 101847451 A CN101847451 A CN 101847451A
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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 a safety injection system, which is used for mitigating an accident and protecting the safety of a reactor core of a nuclear power plant and comprises a high-pressure safety injection pump, a low-pressure safety injection pump, a safety injection tank and a refueling water tank for containing safety injection water, wherein the refueling water tank is positioned in a safety shell of the nuclear power plant; the safety injection tank is connected on a direct pressure vessel injection pipeline by a pipeline provided with a control valve; the high-pressure safety injection pump is connected between the refueling water tank and the direct pressure vessel injection pipeline by a pipeline provided with a control valve; and the low-pressure safety injection pump is connected between the refueling water tank and the direct pressure vessel injection pipeline by a pipeline provided with a control valve. The safety injection system has the advantages of reducing cross pipelines of the system, realizing continuous operation, simplifying the system operation, also strengthening mitigating capability of the system for the serious accident and improving safety of the nuclear power plant.
Description
Technical field
The present invention relates to the improvement of npp safety injected system structure.
Background technology
Safety injection system is called emergence core stacking cool system again, its major function is: when nuclear power generating equipment one circuit system breaks when causing loss of-coolant accident (LOCA), safety injection system guarantees to flood and cool off reactor core to the reactor core water filling, prevent core meltdown, keep the integrality of reactor core; When the generation main steam line breaks, reactor coolant shrinks owing to being subjected to sub-cooled, the voltage stabilizer decline of water table, and safety injection system injects the high concentration boron water to a loop, rebulid the voltage stabilizer water level, rapidly the shutdown and the recovery of critical that prevents reactor owing to cross cold.
Be to realize above-mentioned functions, the situation that one circuit system pressure descended when safety injection system must be according to accident is injected under different stress levels.Safety injection system is become by three groups of subsystems in the prior art:
High-pressure safety injection subsystem: utilize high-pressure safety injection pump 106 (RCV001PO, RCV002PO, RCV003PO) that BAS is injected into reactor coolant loop.Power plant's normal operation period, one is filled pump in the appearance system and normally moves as changing in above-mentioned three pumps, and one is standby, and one is in service mode.On fill pump and control case suction calmly, normal charging stream amount and main pump shaft water shutoff are provided.Under the accident conditions, switch to the high-pressure safety injection pattern, the two pumps operation, one is standby.High-pressure safety injection pump provides high-pressure safety injection from material-changing water tank 101 suctions.
The low pressure peace is annotated subsystem: direct injection stage after the accident and long-term cooling stage, two low pressure safety injection pumps 107 (RIS001PO, RIS002PO) can be injected into boron water reactor coolant loop with the cooling reactor core.The low pressure safety injection pump is also as the fore pump of high-pressure safety injection pump.
Peace is annotated case injection (middle pressure peace is annotated) subsystem: be a passive system, comprise three independently peace annotate casees: (RIS001BA) 108, (RIS002BA) 109, (RIS003BA) 110.During the accident, when the pressure of reactor coolant loop drops to when being lower than peace and annotating case pressure (4.8MPa), the boron water that peace is annotated in the case is expelled in the loop, as shown in Figure 2 automatically.
Existing safety injection system also comprises the boric acid recirculation circuit, mainly injects case 104 (RIS004BA), boric acid ripple tank 103 (RIS021BA) and boric acid recirculation pump 105 (RIS021PO, RIS022PO) by dense boric acid and forms.Major function provides high concentration boron water (7000～9000ppm), and at power plant's normal operation period circulation concentrated boric acid solution, prevent the boron crystallization.
Existing safety injection system is formed comparatively complicated, as shown in Figure 1, its major equipment is annotated case except peace and is arranged in (in the containment) in the reactor building, other equipment (comprise the high and low pressure safety injection pump, boric acid is at ebullator, and dense boric acid injects case, boric acid ripple tank and material-changing water tank etc.) all be positioned at fuel factory building (containment is outer).Among Fig. 1, the stand-by state of the corresponding RIS of valve state system,
Represent valve in opening,
The expression valve in off position.Existing safety injection system has also adopted more cross pipeline except needing back-up systems such as emergency power pack, complicated chilled water and HVAC.The setting of dense boric acid injection case and circulating line thereof has increased the complicacy of system especially greatly.The operation of system is also rather complicated, not only will carry out a large amount of valve operations, also related to high-pressure safety injection pump/on fill the switching of pump operation pattern.After accident, on fill pump and switch to the high-pressure safety injection pattern by last mold filling formula, the water sucking mouth of pump holds control case 102 and switches to material-changing water tank by changing the appearance system; And the switching in different phase peace water filling source after the accident, switch to melt pit as the suction inlet of high-low pressure safety injection pump by material-changing water tank.
Because existing safety injection system is formed complicated, move loaded down with trivial detailsly, cause generation people in system's operational process to increase greatly because of the possibility of mistake.And a large amount of practices statistics shows, safe major event and the fault of nuclear power station more than 50% all caused because of mistake by the people.
In addition, existing safety injection system major accident processing power deficiency will become the key factor that restricts its market competitiveness.
For this reason, needing to use for reference the advanced nuclear power technology in the world makes improvements.
Summary of the invention
The technical problem to be solved in the present invention is, at the above-mentioned defective of prior art, provide a kind of designs simplification, operation steps few, can effectively reduce the npp safety injected system that the people hinders and can significantly improve the major accident processing power for some reason.
The technical solution adopted for the present invention to solve the technical problems is:
Constructed a kind of safety injection system, the safety that is used for alleviation accident, protection nuclear power plant reactor core comprises high-pressure safety injection pump, low pressure safety injection pump and peace notes case, also comprises being used to hold the material-changing water tank of pacifying water filling, wherein, described material-changing water tank is positioned at the containment of nuclear power plant;
Described peace is annotated case and is connected on the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control;
Described high-pressure safety injection pump is connected between described material-changing water tank and the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control;
Described low pressure safety injection pump is connected between described material-changing water tank and the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control.
Safety injection system of the present invention, wherein, described high-pressure safety injection pump comprises the first separate high-pressure safety injection pump and second high-pressure safety injection pump, wherein,
Described first high-pressure safety injection pump is connected between the described material-changing water tank and the first direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control;
Described second high-pressure safety injection pump is connected between the described material-changing water tank and the second direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control.
Safety injection system of the present invention, wherein, described peace is annotated case and is comprised that first peace is annotated case and second peace is annotated case; Described first peace is annotated case and is connected on the first direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control; Described second peace is annotated case and is connected on the second direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control.
Safety injection system of the present invention also comprises the automatically unloading subsystem.Described automatically unloading subsystem comprises two series, and each series comprises the pressure relief valve of three grades of parallel connections; Described automatically unloading subsystem connects described material-changing water tank and voltage stabilizer, the steam in the voltage stabilizer is discharged into described material-changing water tank, the fast controllable release of realization response reactor coolant system.。
Beneficial effect of the present invention is, adopts direct pressure container injection system, reduces system's cross pipeline, system is formed greatly simplify.Material-changing water tank is positioned at containment, can the realization accident after the continuous operation of safety injection system do not switch, system's operation is simplified, reliability improves.In addition, set up the automatically unloading system, can rationally reduce the high-pressure safety injection lift of pump, and can strengthen its severe accident relieving ability, improved the security of nuclear power plant for existing safety injection system.
Description of drawings
The invention will be further described below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is high pressure of the prior art and low-voltage safety injected system structural representation;
Fig. 2 is the middle safety injection system structural representation of pressing of the prior art
Fig. 3 is the safety injection system structural representation of the embodiment of the invention.
Embodiment
Below in conjunction with diagram, the preferred embodiments of the present invention are described in detail.
The safety injection system structural representation of the nuclear power plant of the embodiment of the invention as shown in Figure 3, safety injection system after the improvement is compared with original system, still be the safety injection mode that has adopted under high, medium and low three stress levels, but the composition of system is but greatly simplified.Safety injection system after the improvement mainly comprises high-pressure safety injection pump, low pressure safety injection pump 206, and peace is annotated case, also comprises being used to hold the material-changing water tank 207 of pacifying water filling.Wherein, high-pressure safety injection pump can connect material-changing water tank 207 and direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control, as shown in Figure 3.The low pressure safety injection pump connects material-changing water tank 207 and direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control.Peace is annotated case and is connected on the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control.Wherein, direct pressure container injection pipeline is connected on nuclear power plant's pressure vessel.Safety injection system after the improvement has adopted the direct injection system of pressure vessel to replace original cold leg injection pattern, will pacify water filling and squeeze into reactor core.
In the present embodiment, two independent high-pressure safety injection pumps can be set specifically, comprise: first high-pressure safety injection pump 204 and second high-pressure safety injection pump 205.First high-pressure safety injection pump 204 is connected between the material-changing water tank 207 and the first direct pressure container injection pipeline 202 by the pipeline that is provided with by-pass valve control; Second high-pressure safety injection pump 205 is connected between the material-changing water tank 207 and the second direct pressure container injection pipeline 203 by the pipeline that is provided with by-pass valve control.Wherein, the first direct pressure container injection pipeline 202 and the second direct pressure container injection pipeline 203 all are connected on the pressure vessel.Above-mentioned set-up mode can be realized safety injection system and the complete independence of changing the appearance system, need not to carry out the switching of pump operation pattern after the accident, has simplified the operation of system after accident.By two independent high-pressure safety injection pumps are set, the system that can make possesses two fully independently series, satisfies the requirement of single failure criteria, reduces the potential risk that high-pressure safety injection lost efficacy.
In the present embodiment, adopt the direct injection system of pressure vessel to replace original cold leg injection pattern, under the accident conditions, can utilize the high and low pressure safety injection pump that the boron water in the material-changing water tank 207 is squeezed into reactor core by direct pressure container injection pipeline.Adopt this mode can reduce the employing of female pipeline section, and three peace notes casees of original system can be become two, comprise that promptly first peace is annotated case 209 and second peace is annotated case 210, as shown in Figure 3.Wherein, first peace is annotated case 209 and is connected to the first direct pressure container injection pipeline 202 by the pipeline that is provided with by-pass valve control.Second peace is annotated case 210 and is connected to the second direct pressure container injection pipeline 203 by the pipeline that is provided with by-pass valve control.The core deluge ability that each peace is annotated case increases to 100% by original 50%.Like this, safety injection system just can have been simplified the composition of system on the basis of improving system reliability, has reduced the manufacture difficulty of trunk line simultaneously.
In the present embodiment, change the arrangement of material-changing water tank 207, be placed in the containment of nuclear power plant, and make the suction water source of high and low pressure safety injection pump be always material-changing water tank 207 in the containment, make it as accident after unique peace water filling source of high and low pressure safety injection pump.Therefore, need not to pacify the switching in water filling source after the accident, can realize the continuous operation of safety injection system and the operation steps after the minimizing accident, avoided contingent people because of mistake, reduce system running pattern and switched the potential risk that causes safety injection system to lose efficacy, thereby the reliability of system is provided, has strengthened the security of nuclear power plant.
In the present embodiment, cancel dense boric acid and inject case and recirculation circuit thereof, and suitably improve boron concentration in the material-changing water tank 207, the assurance system is failing in the anticipated transient of emergency shut-down (ATWS) incident, enough boronation abilities are provided, under the prerequisite that guarantees power plant safety, simplify the operation of power plant's normal operation period safety injection system greatly.
For improving system's major accident processing power, the safety injection system of present embodiment is set up between the material-changing water tank 207 in voltage stabilizer 208 and containment and is unloaded subsystem 201 automatically, as shown in Figure 3.Automatically unloading subsystem 201 is made up of two series, each series comprises the pressure relief valve of three grades of parallel connections, each series all is connected between described material-changing water tank 207 and the voltage stabilizer 208, be used to provide the discharge-channel of safe level, with the incondensable gas or the steam of the high point of voltage stabilizer 208, pressure vessel upper cover or reactor coolant loop.Accident conditions down by this system with the material-changing water tank 207 to the containment of the discharge of steam in the voltage stabilizer 208, but quick, the controlled release of realization response reactor coolant system.This system and high-pressure safety injection pump acting in conjunction, can be in super design reference accident or major accident that forfeiture is all fed water, benefit is let out in realization one loop fast, peace is annotated and was lost efficacy under the loop high-pressure situations that avoids a nasty accident, guarantee to pacify the beam amount and inject reactor core timely and effectively, thereby the alleviation accident process prevents the initial failure of containment.Simultaneously, adopt above-mentioned technology also to reduce requirement, can rationally reduce the performance requirement of high-pressure safety injection pump high-pressure safety injection subsystem injection pressure.
When present embodiment can the cut accident take place in nuclear power plant one loop, the situation according to a circuit system pressure descends realized under the different stress levels to the reactor core water filling.Under a loop large break accident conditions, annotate signal once receiving peace, system will carry out following operation:
1) high-pressure safety injection subsystem: start high-pressure safety injection pump, open isolation valve on the high-pressure safety injection pump suction line and the main isolating valve between high-pressure safety injection pump and the direct pressure container injection pipeline, enter pressure vessel by direct pressure container injection pipeline after making boron water in the material-changing water tank through the high-pressure safety injection pump supercharging;
2) press peace to annotate subsystem in: when a circuit pressure drops to when being lower than peace and annotating case pressure, the boron water that peace is annotated in the case will be expelled under the effect of pressurized nitrogen in the loop automatically;
3) the low pressure peace is annotated subsystem: start the low pressure safety injection pump, open isolation valve on the low pressure safety injection pump upstream line and the main isolating valve between low pressure safety injection pump and the direct pressure container injection pipeline, enter pressure vessel by direct pressure container injection pipeline after making the boron water process low pressure safety injection pump supercharging in the material-changing water tank, realize low head injection;
4) after the accident 12 hours, the operations staff can set up the heat pipe section and direct pressure container injection pipeline is injected simultaneously, prevents that boric acid is at the reactor core intercrystalline.
After adopting technique scheme, safety injection system cancellation and the equipment dual-purpose of changing the appearance system are provided with independently high-pressure safety injection pump, and adopt direct pressure container injection system, reduce cross pipeline, and system forms greatly to be simplified.Safety injection system after the improvement has been realized continuous operation, and need not switch peace water filling source, and system's operation is simplified, and reliability improves.In addition, owing to set up the automatically unloading subsystem, can strengthen the severe accident relieving ability of safety injection system, and can rationally reduce the high-pressure safety injection lift of pump.Safety injection system after the improvement satisfies the URD requirement.
Should be understood that, for those of ordinary skills, can be improved according to the above description or conversion, and all these improvement and conversion all should belong to the protection domain of claims of the present invention.
Claims (4)
1. safety injection system, the safety that is used for alleviation accident, protection nuclear power plant reactor core, comprise high-pressure safety injection pump, low pressure safety injection pump (206) and peace notes case, also comprise and be used to hold the material-changing water tank (207) of pacifying water filling, it is characterized in that described material-changing water tank (207) is positioned at the containment of nuclear power plant;
Described peace is annotated case and is connected on the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control;
Described high-pressure safety injection pump is connected between described material-changing water tank (207) and the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control;
Described low pressure safety injection pump (206) is connected between described material-changing water tank (207) and the direct pressure container injection pipeline by the pipeline that is provided with by-pass valve control.
2. safety injection system according to claim 1 is characterized in that, described high-pressure safety injection pump comprises separate first high-pressure safety injection pump (204) and second high-pressure safety injection pump (205), wherein,
Described first high-pressure safety injection pump (204) is connected between the described material-changing water tank (207) and the first direct pressure container injection pipeline (202) by the pipeline that is provided with by-pass valve control;
Described second high-pressure safety injection pump (205) is connected between the described material-changing water tank (207) and the second direct pressure container injection pipeline (203) by the pipeline that is provided with by-pass valve control.
3. safety injection system according to claim 2 is characterized in that, described peace is annotated case and comprised that first peace is annotated case (209) and second peace is annotated case (210); Described first peace is annotated case (209) and is connected on the first direct pressure container injection pipeline (202) by the pipeline that is provided with by-pass valve control; Described second peace is annotated case (210) and is connected on the second direct pressure container injection pipeline (203) by the pipeline that is provided with by-pass valve control.
4. safety injection system according to claim 3 is characterized in that, described safety injection system also comprises automatically unloading subsystem (201); Described automatically unloading subsystem (201) comprises two series, and each series comprises the pressure relief valve of three grades of parallel connections; Described automatically unloading subsystem is connected between described material-changing water tank (207) and the voltage stabilizer (208), is used for the steam of voltage stabilizer (208) is discharged into described material-changing water tank (207).
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| CN2009101082309A CN101847451B (en) | 2009-06-19 | 2009-06-19 | Safety injection system |
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| CN2009101082309A CN101847451B (en) | 2009-06-19 | 2009-06-19 | Safety injection system |
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Cited By (24)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN102737739A (en) * | 2011-04-15 | 2012-10-17 | 韩国原子力研究院 | Passive high pressure safety injection tank system (hpsit) for responding to station blackout (sbo) and loss-of-coolant accidents (loca) |
| CN103187110A (en) * | 2012-01-03 | 2013-07-03 | 陈光焕 | Nuclear energy steam self-compression water adding rod |
| CN103426485A (en) * | 2012-05-25 | 2013-12-04 | 国家核电技术有限公司 | Method used for preventing pressure vessels from melting damages caused by molten materials in reactors, and system used for method |
| CN103545001A (en) * | 2012-07-12 | 2014-01-29 | 韩国原子力硏究院 | Passive safety injection system using safety injection tank |
| WO2014048292A1 (en) * | 2012-09-27 | 2014-04-03 | 中国核电工程有限公司 | Combined active and passive reactor core water injection and heat removal apparatus |
| CN103778975A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Passive reactor core water-supplement system of pressure vessel and passive reactor core water-supplement method using the same |
| CN103811083A (en) * | 2012-11-14 | 2014-05-21 | 中国广东核电集团有限公司 | Safety injection system of nuclear power station and method for clearing injection pipeline |
| CN103871505A (en) * | 2012-12-11 | 2014-06-18 | 中国核动力研究设计院 | Automatic rapid cooling method for nuclear power plant steam discharge system |
| CN103971764A (en) * | 2013-02-01 | 2014-08-06 | 韩国原子力研究院 | Multi stage safety injection device and passive safety injection system having the same |
| CN104064230A (en) * | 2013-03-21 | 2014-09-24 | 中广核（北京）仿真技术有限公司 | Nuclear reactor double-end safety injection system |
| CN104347132A (en) * | 2013-07-26 | 2015-02-11 | 中广核工程有限公司 | Method for protecting main pump in nuclear power plant shutdown condition |
| CN104536400A (en) * | 2014-12-13 | 2015-04-22 | 国核自仪***工程有限公司 | Nuclear power station DCS simulation modeling method |
| CN105122375A (en) * | 2013-03-12 | 2015-12-02 | BWXTm动力股份有限公司 | RWET passive emergency core flow |
| CN105139902A (en) * | 2015-07-01 | 2015-12-09 | 中国核电工程有限公司 | Nuclear-power-plant improved type medium-pressure safety injection system |
| CN105845187A (en) * | 2016-05-18 | 2016-08-10 | 中广核研究院有限公司 | Severe nuclear power plant accident mitigating system |
| CN107945893A (en) * | 2017-10-09 | 2018-04-20 | 中广核研究院有限公司 | A kind of nuclear power plant's emergence core stacking cool system |
| CN108091407A (en) * | 2017-11-10 | 2018-05-29 | 中广核研究院有限公司 | High-pressure injection system and its Safety Injection 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 |
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| GB2523949B (en) * | 2012-12-11 | 2020-07-01 | Nuclear Power Inst China | High-pressure safe injection system for nuclear power stations |
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| CN102737739A (en) * | 2011-04-15 | 2012-10-17 | 韩国原子力研究院 | Passive high pressure safety injection tank system (hpsit) for responding to station blackout (sbo) and loss-of-coolant accidents (loca) |
| CN102737739B (en) * | 2011-04-15 | 2015-12-09 | 韩国原子力研究院 | The non-active high-voltage safety of reply station blackout and loss-of-coolant accident (LOCA) injects case system |
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| CN103187110A (en) * | 2012-01-03 | 2013-07-03 | 陈光焕 | Nuclear energy steam self-compression water adding rod |
| CN103187110B (en) * | 2012-01-03 | 2015-11-25 | 陈光焕 | Nuclear steam dead weight water-adding rod |
| CN103426485A (en) * | 2012-05-25 | 2013-12-04 | 国家核电技术有限公司 | Method used for preventing pressure vessels from melting damages caused by molten materials in reactors, and system used for method |
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| CN103545001B (en) * | 2012-07-12 | 2016-08-17 | 韩国原子力硏究院 | Use the passive safety injection system of Safety Injection case |
| WO2014048292A1 (en) * | 2012-09-27 | 2014-04-03 | 中国核电工程有限公司 | Combined active and passive reactor core water injection and heat removal apparatus |
| CN103778975A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Passive reactor core water-supplement system of pressure vessel and passive reactor core water-supplement method using the same |
| CN103811083A (en) * | 2012-11-14 | 2014-05-21 | 中国广东核电集团有限公司 | Safety injection system of nuclear power station and method for clearing injection pipeline |
| GB2523949B (en) * | 2012-12-11 | 2020-07-01 | Nuclear Power Inst China | High-pressure safe injection system for nuclear power stations |
| CN103871505A (en) * | 2012-12-11 | 2014-06-18 | 中国核动力研究设计院 | Automatic rapid cooling method for nuclear power plant steam discharge system |
| CN103971764A (en) * | 2013-02-01 | 2014-08-06 | 韩国原子力研究院 | Multi stage safety injection device and passive safety injection system having the same |
| US9859027B2 (en) | 2013-02-01 | 2018-01-02 | Korea Atomic Energy Research Institute | Multi stage safety injection device and passive safety injection system having the same |
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| US10720248B2 (en) | 2013-03-15 | 2020-07-21 | Bwxt Mpower, Inc. | Passive techniques for long-term reactor cooling |
| US11355253B2 (en) | 2013-03-15 | 2022-06-07 | Bwxt Mpower, Inc. | Passive techniques for long-term reactor cooling |
| CN104064230A (en) * | 2013-03-21 | 2014-09-24 | 中广核（北京）仿真技术有限公司 | Nuclear reactor double-end safety injection system |
| CN104347132A (en) * | 2013-07-26 | 2015-02-11 | 中广核工程有限公司 | Method for protecting main pump in nuclear power plant shutdown condition |
| CN104536400A (en) * | 2014-12-13 | 2015-04-22 | 国核自仪***工程有限公司 | Nuclear power station DCS simulation modeling method |
| CN105139902A (en) * | 2015-07-01 | 2015-12-09 | 中国核电工程有限公司 | Nuclear-power-plant improved type medium-pressure safety injection system |
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Address after: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District Co-patentee after: CHINA GENERAL NUCLEAR POWER Corp. Patentee after: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd. Address before: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District Co-patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. Patentee before: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd. |
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