CN113436760A - Debugging test method for heat removal capacity of passive waste heat removal system in thermal state - Google Patents
Debugging test method for heat removal capacity of passive waste heat removal system in thermal state Download PDFInfo
- Publication number
- CN113436760A CN113436760A CN202110697124.XA CN202110697124A CN113436760A CN 113436760 A CN113436760 A CN 113436760A CN 202110697124 A CN202110697124 A CN 202110697124A CN 113436760 A CN113436760 A CN 113436760A
- Authority
- CN
- China
- Prior art keywords
- heat removal
- waste heat
- secondary side
- removal system
- steam generator
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
-
- 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
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a debugging test method for the heat removal capacity of a passive waste heat removal system in a thermal state, which comprises the following steps: controlling a reactor coolant system and a secondary loop system to keep a hot shutdown working condition state, and controlling three main pumps to be in a shutdown state; improving the atmospheric vent valve discharge setting value of the steam bypass system; regulating the water level and pressure of the pressure stabilizer to automatic control; closing an outlet regulating valve of a feed pump of the main water supply system and isolating the main water supply system; putting the secondary side passive waste heat discharge system of the steam generator into operation, and putting the system into an emergency water supply tank; monitoring the change of the average temperature of the hot section, and recording related thermal parameters of a secondary side passive waste heat discharge system of the steam generator; when the average temperature of the hot section is reduced to a preset temperature, the secondary side passive waste heat discharge system of the steam generator is stopped; and calculating heat exchange power by using the obtained related thermal parameters, and verifying the heat exchange capacity of the passive waste heat discharge system. The invention is used for verifying the heat exchange capability of the secondary side passive waste heat discharge system of the steam generator.
Description
Technical Field
The invention belongs to the technical field of thermal engineering, and particularly relates to a debugging test method for heat removal capacity of a passive waste heat removal system in a thermal state.
Background
The national third-generation nuclear power technology-Hualong I nuclear power plant emergency reactor core waste heat deriving system is designed in a mode of combining active and passive, the passive system is a Steam Generator (SG) secondary side passive waste heat discharge system (PRS), the system is one of Hualong I three large passive systems, and the system has an important function of relieving the accident consequence of the over-design basis. The design scheme of the secondary side passive waste heat discharge system of the steam generator adopts a form of being connected with the secondary side of the steam generator, each steam generator corresponds to one PRS series, and each PRS series comprises an emergency waste heat discharge cooler, two emergency water supply tanks, a heat exchange water tank, necessary valves, pipes and instruments (as shown in figure 1). The system is a two-phase natural circulation phenomenon during operation, is used as a key system for responding and relieving Hualong I super-design reference accidents, is designed for the first time in China, and must be used for heat extraction capability verification experiments. However, no engineering debugging experience exists at home and abroad. Therefore, a debugging scheme of a novel two-phase passive residual heat removal system needs to be researched and designed.
Disclosure of Invention
The invention provides a debugging test method for the heat removal capacity of a passive waste heat removal system in a thermal state. The method is used for verifying the heat exchange capability of the secondary side passive waste heat removal system of the steam generator, and is based on the test of the SG secondary side passive waste heat removal system installed in the nuclear power plant, and the debugging test is carried out after the reactor is charged and before the first criticality.
The invention is realized by the following technical scheme:
the debugging test method for the heat removal capacity of the passive waste heat removal system in the thermal state comprises the following steps:
step 4, closing an outlet regulating valve of a feed pump of the main water supply system, and isolating the main water supply system;
5, operating the secondary side passive waste heat discharge system of the steam generator and putting the secondary side passive waste heat discharge system into an emergency water supply tank;
7, stopping the secondary side passive waste heat removal system of the steam generator after the average temperature of the hot section is reduced to a preset temperature;
and 8, calculating heat exchange power by using the related thermal parameters obtained in the step 6, and verifying the heat exchange capacity of the passive waste heat removal system.
Preferably, in step 2 of the method, the exhaust setting value of the atmospheric vent valve of the steam bypass system is increased to any value between 8.2MPa and the opening setting value of the steam safety valve.
Preferably, step 5 of the present invention implements the operation of the passive residual heat removal system by opening the condensate isolating valves of the secondary side passive residual heat removal system of one or three rows of steam generators.
Preferably, the relevant thermal parameters recorded in step 6 of the present invention include the condensed water flow, the steam pressure and the condensed water temperature of the passive residual heat removal system.
Preferably, step 7 of the invention realizes the shutdown of the passive residual heat removal system by closing the condensation isolation valve opened in step 5.
Preferably, the preset temperature of step 7 of the present invention is 20 ℃ to 30 ℃.
Preferably, step 8 of the present invention verifies the heat exchange capability of the system by comparing the calculated heat exchange power with the acceptance criterion.
Preferably, step 1 of the present invention further comprises: the pressure and the water level of the voltage stabilizer are controlled to ensure that the risk of exposing an electric heater of the voltage stabilizer, the risk of exposing a heat transfer pipe of a steam generator and the risk of damaging a pressure boundary of a loop of the reactor cannot occur in the test process.
Preferably, the method of the invention is used for carrying out a test based on a secondary side passive waste heat discharge system of a steam generator installed in a nuclear power plant, and the debugging test is carried out after the reactor is charged and before the first criticality.
The invention has the following advantages and beneficial effects:
the test method provided by the invention is suitable for verifying the heat removal capability of the secondary side passive waste heat removal system of the steam generator of the nuclear power plant, and can achieve the aim of verifying the heat removal capability of the secondary side passive waste heat removal system of the steam generator and avoid possible thermal safety risks of a reactor, including the exposure risk of an electric heater of a voltage stabilizer, the exposure risk of a heat transfer pipe of the steam generator, the damage risk of a pressure boundary of a loop of the reactor and the like.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic flow diagram of a Hualong I reactor system. Wherein, 1-a pressure vessel; 2-control rod drive mechanism; 3-a voltage stabilizer; 4-a steam generator; 5-main pump; 6-auxiliary spraying; 7-a spray valve; 8-main water supply pipe; 9-main steam line; 10-emergency waste heat discharge cooler; 11-a heat exchange water tank; 12-emergency water replenishing tank; 13-a condensate isolation valve; 14-emergency water replenishing tank condensation isolation valve; 15-atmosphere by-pass valve.
FIG. 2 is a schematic flow chart of the method of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Examples
The test method is developed in the thermal state, and can verify whether the heat removal capacity of the secondary side passive waste heat removal system of the steam generator meets the design requirement of the system or not.
The method of the embodiment is based on the test of the SG secondary side passive residual heat removal system installed in the nuclear power plant, the debugging test should be performed after the reactor is charged and before the first criticality, and as shown in fig. 2, the method includes the following steps:
the method comprises the following steps: setting the initial conditions of the test: controlling a reactor coolant system and a secondary loop system of the nuclear power plant to keep a hot shutdown working condition state, and controlling three main pumps to be in a shutdown state; meanwhile, the pressure and the water level of the voltage stabilizer are controlled, so that the exposure risk of an electric heater of the voltage stabilizer, the exposure risk of a heat transfer pipe of a steam generator and the damage risk of a pressure boundary of a loop of the reactor can be avoided in the test process;
step two: the exhaust setting value of an atmospheric vent valve of the steam bypass exhaust system is increased to any value between 8.2MPa and the opening setting value of a steam safety valve;
step three: regulating the water level and pressure of the pressure stabilizer to automatic control;
step four: closing an outlet regulating valve of a feed pump of the main water supply system and isolating the main water supply system;
step five: putting the secondary side passive waste heat discharge system of the steam generator into operation, and putting the system into an emergency water supply tank; for example, the operation of the passive residual heat removal system can be realized by opening the condensate isolating valves of the secondary side passive residual heat removal system of one or three rows of steam generators;
step six: monitoring the change of the average temperature of the hot section, and recording thermodynamic parameters such as condensed water flow, steam pressure, condensed water temperature and the like of the SG secondary side passive waste heat discharge system;
step seven: when the average temperature of the hot section is reduced to any value between 20 ℃ and 30 ℃, closing the condensate isolating valves of the secondary side passive waste heat discharge system of the one or three rows of steam generators opened in the step five, and stopping the secondary side passive waste heat discharge system of the steam generators;
step eight: and calculating heat exchange power by using relevant thermal parameters (condensed water flow, steam pressure and condensed water temperature) measured in the test, and comparing the heat exchange power with an acceptance criterion to verify the heat exchange capacity of the system.
The device used and related to the debugging test method comprises: the system comprises a reactor main coolant pump, a steam generator secondary side passive waste heat discharge system, a main water supply system valve, a steam bypass discharge system, a voltage stabilizer water level control system, a voltage stabilizer pressure control system and the like. The devices are all existing devices of the reactor, and no additional device is added.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (9)
1. The debugging test method for the heat removal capacity of the passive waste heat removal system in the thermal state is characterized by comprising the following steps of:
step 1, controlling a reactor coolant system and a secondary loop system of a nuclear power plant to keep a hot shutdown working condition state, and controlling three main pumps to be in a shutdown state;
step 2, improving an atmospheric discharge valve discharge setting value of the steam bypass system;
step 3, adjusting the water level and the pressure of the voltage stabilizer to automatic control;
step 4, closing an outlet regulating valve of a feed pump of the main water supply system, and isolating the main water supply system;
5, operating the secondary side passive waste heat discharge system of the steam generator and putting the secondary side passive waste heat discharge system into an emergency water supply tank;
step 6, monitoring the change of the average temperature of the hot section, and recording related thermal parameters of a secondary side passive waste heat discharge system of the steam generator;
7, stopping the secondary side passive waste heat removal system of the steam generator after the average temperature of the hot section is reduced to a preset temperature;
and 8, calculating heat exchange power by using the related thermal parameters obtained in the step 6, and verifying the heat exchange capacity of the passive waste heat removal system.
2. The debugging test method for the heat removal capacity of the passive residual heat removal system in the thermal state according to claim 1, wherein the step 2 is specifically to increase the atmospheric vent valve emission setting value of the steam bypass system to any value between 8.2MPa and the steam safety valve opening setting value.
3. The debugging test method for the heat removal capacity of the passive residual heat removal system in the thermal state according to claim 1, wherein the step 5 is implemented by opening one or three rows of condensation isolation valves of the secondary side passive residual heat removal system of the steam generator.
4. The debugging test method for heat removal capability of the passive residual heat removal system in the thermal state according to claim 1, wherein the relevant thermal parameters recorded in the step 6 comprise condensed water flow, steam pressure and condensed water temperature of the passive residual heat removal system.
5. The debugging test method for the heat removal capacity of the passive residual heat removal system in the thermal state according to claim 3, wherein the step 7 is implemented by closing the condensate isolation valve opened in the step 5 to shut down the passive residual heat removal system.
6. The debugging test method for the heat removal capacity of the passive residual heat removal system in the thermal state according to claim 1, wherein the preset temperature in the step 7 is 20 ℃ to 30 ℃.
7. The debugging test method for heat removal capability of the passive residual heat removal system in a thermal state according to any one of claims 1-6, wherein the step 8 is implemented by comparing the calculated heat exchange power with an acceptance criterion, so as to verify the heat exchange capability of the system.
8. The debugging test method for the heat removal capacity of the passive residual heat removal system in the thermal state according to any one of claims 1 to 6, wherein the step 1 further comprises: the pressure and the water level of the voltage stabilizer are controlled, and the exposure risk of an electric heater of the voltage stabilizer, the exposure risk of a heat transfer pipe of a steam generator and the damage risk of a pressure boundary of a loop of the reactor can be avoided in the test process.
9. The method for debugging and testing the heat removal capability of the passive residual heat removal system in the thermal state according to claim 1, wherein the method is based on a secondary side passive residual heat removal system of a steam generator installed in a nuclear power plant, and the debugging test is carried out after reactor charging and before the first criticality.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110697124.XA CN113436760A (en) | 2021-06-23 | 2021-06-23 | Debugging test method for heat removal capacity of passive waste heat removal system in thermal state |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110697124.XA CN113436760A (en) | 2021-06-23 | 2021-06-23 | Debugging test method for heat removal capacity of passive waste heat removal system in thermal state |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN113436760A true CN113436760A (en) | 2021-09-24 |
Family
ID=77753491
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110697124.XA Pending CN113436760A (en) | 2021-06-23 | 2021-06-23 | Debugging test method for heat removal capacity of passive waste heat removal system in thermal state |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113436760A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114251646A (en) * | 2021-11-15 | 2022-03-29 | 中广核研究院有限公司 | Steam generator liquid level control method suitable for main pump start-stop working condition |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104299661A (en) * | 2014-10-11 | 2015-01-21 | 中广核工程有限公司 | Transient test control method and system used in debugging and starting process of nuclear power station |
| KR101651466B1 (en) * | 2015-04-02 | 2016-08-29 | 한국원자력연구원 | Verification test device for passive residual heat removal system of a research reactor |
| CN106024079A (en) * | 2016-08-02 | 2016-10-12 | 合肥通用机械研究院 | Passive residual heat removal circulation performance test system and test method |
| CN106653109A (en) * | 2016-12-30 | 2017-05-10 | 福建福清核电有限公司 | Experimental research device for secondary side passive residual heat removal system (PRS) |
-
2021
- 2021-06-23 CN CN202110697124.XA patent/CN113436760A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104299661A (en) * | 2014-10-11 | 2015-01-21 | 中广核工程有限公司 | Transient test control method and system used in debugging and starting process of nuclear power station |
| KR101651466B1 (en) * | 2015-04-02 | 2016-08-29 | 한국원자력연구원 | Verification test device for passive residual heat removal system of a research reactor |
| CN106024079A (en) * | 2016-08-02 | 2016-10-12 | 合肥通用机械研究院 | Passive residual heat removal circulation performance test system and test method |
| CN106653109A (en) * | 2016-12-30 | 2017-05-10 | 福建福清核电有限公司 | Experimental research device for secondary side passive residual heat removal system (PRS) |
Non-Patent Citations (5)
| Title |
|---|
| 于雷 等: "核动力装置非能动余热排出系统的数学建模与仿真", 《系统仿真学报》 * |
| 吴李兴: ""华龙一号"机组二次侧非能动余热排出系统运行分析", 《核科学与工程》 * |
| 朱达睿 等: "核电厂热试期间二回路非能动自然循环试验分析", 《科技与创新》 * |
| 鲜麟 等: "基于热管技术的非能动余热排出系统换热能力研究", 《核动力工程》 * |
| 黄宗仁 等: "华龙一号调试首堆试验研究与设计", 《核动力工程》 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114251646A (en) * | 2021-11-15 | 2022-03-29 | 中广核研究院有限公司 | Steam generator liquid level control method suitable for main pump start-stop working condition |
| CN114251646B (en) * | 2021-11-15 | 2023-12-26 | 中广核研究院有限公司 | Steam generator liquid level control method suitable for start-stop working condition of main pump |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| KR101973996B1 (en) | External Reactor Vessel Cooling and Electric Power Generation System | |
| KR101988265B1 (en) | Cooling Facility in a Reactor Vessel and Electric Power Generation System | |
| CN113436760A (en) | Debugging test method for heat removal capacity of passive waste heat removal system in thermal state | |
| CN114234173B (en) | Nuclear power station steam generator cooling system | |
| CN111753394A (en) | Design method for rapid cooling function debugging of primary circuit of advanced pressurized water reactor nuclear power plant | |
| JP2017067725A (en) | Alternative circulating and cooling method of emergency reactor core cooling system and nuclear power plant | |
| CN109801722B (en) | Heat exchange test method and system for plate heat exchanger of SEU (continuous emission unit) system of nuclear power plant | |
| KR102214119B1 (en) | Coolant recirculation system of nuclear power plant | |
| CN113421671A (en) | Debugging test method for heat removal capacity of passive waste heat removal system in thermal state | |
| CN113571211B (en) | Nuclear power system and method and primary loop system thereof as well as reactor overpressure protection system and method | |
| JP2017538126A (en) | How to manage a shutdown of a pressurized water reactor | |
| KR101278906B1 (en) | Apparatus for preventing thermal shock having a condensate mixing storage tank on condensate return line | |
| KR20130004305A (en) | Facility for producing energy using a gas-cooled fast reactor | |
| JP7228477B2 (en) | Residual heat removal equipment, its operating method and residual heat removal method | |
| KR100448876B1 (en) | Emergency feed water system in nuclear power plant | |
| CN215927489U (en) | Non-nuclear steam flushing system of high-temperature gas cooled reactor | |
| CN217584390U (en) | High temperature gas cooled reactor steam recovery system | |
| CN215988120U (en) | Containment cooling water cooling device and passive containment cooling system | |
| CN215988119U (en) | Steam generator cooling system used after emergency shutdown of high-temperature gas cooled reactor | |
| Tian et al. | Design characteristics analysis of RTVO for a nuclear power plant | |
| KR20220132303A (en) | Liquid air energy storage system linked to Nuclear power plant | |
| Wu et al. | Study on Passive Pulse Cooling Method of Secondary Side in PWR Nuclear Power Plant | |
| Liu et al. | Transient Analysis of CP300 Based on RELAP5/MOD3. 4 | |
| Wenying et al. | Analysis of the Thermal Performance of the Passive Containment Cooling System Based on Heat Pipe Technology Under Nuclear Accidents | |
| Borisov et al. | Determination of the LB LOCA Ranges in the Containment for the Purposes of PSA Level 1 for KNPP |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20210924 |