WO2015014047A1 - Safety injection system of hot leg of nuclear power station - Google Patents
Safety injection system of hot leg of nuclear power station Download PDFInfo
- Publication number
- WO2015014047A1 WO2015014047A1 PCT/CN2013/087741 CN2013087741W WO2015014047A1 WO 2015014047 A1 WO2015014047 A1 WO 2015014047A1 CN 2013087741 W CN2013087741 W CN 2013087741W WO 2015014047 A1 WO2015014047 A1 WO 2015014047A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- hot section
- safety injection
- electric isolation
- isolation valve
- hot
- Prior art date
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Classifications
-
- 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
-
- 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
Definitions
- the invention belongs to the field of nuclear power safety, and more particularly to a safety injection system for a thermal section of a nuclear power plant capable of improving the probability of successful safety injection of a hot section under accident conditions.
- the RIS system safety injection system
- the RHR system main heat removal system
- the hot section injection pipeline of the RIS system and the hot section water intake pipeline of the RHR system are combined into one, so there is no need to install a separate RHR system, thus saving equipment and improving the economic efficiency of the nuclear power plant. the goal of.
- the above RIS system isolates the thermal circuit of the RIS system from the primary circuit of the reactor coolant system through two electric isolation valves located on the combined pipeline; in normal shutdown conditions, when the primary circuit When the pressure and temperature are reduced to the access conditions of the RHR system, the residual heat is discharged under the shutdown condition by opening two electric isolation valves; in the accident condition, when the hot section safety injection function needs to be performed, the operation is required.
- Two electric isolation valves are opened in the main control room to ensure that the boron-containing water can be injected from the hot section. In other words, whether the electric isolation valve can be successfully opened determines whether the hot section safety injection can be successful.
- the object of the present invention is to provide a safety injection system for a thermal power station of a nuclear power plant capable of improving the probability of successful safety injection in a hot section under accident conditions.
- the present invention provides a nuclear power plant hot section safety injection system comprising a hot section connecting pipe with two electric isolation valves spaced apart, and a heat section safety section provided with at least one check valve Injecting the pipe, the two ends of the hot section safety injection pipe are respectively connected to the hot section connecting pipe so that the check valve thereon is connected in parallel with at least one of the two electric isolation valves of the hot segment connecting pipe.
- one end of the hot section connecting pipe is connected to a low pressure safety injection pipe, and the other end is connected to a hot section of the first circuit of the reactor coolant system;
- the valves are a first electric isolation valve adjacent to the low pressure safety injection conduit and a second electric isolation valve adjacent to the hot section of the primary coolant of the reactor coolant system.
- two check valves are connected in parallel with the first electric isolation valve and the second electric isolation valve.
- one end of the hot section safety injection pipe is connected at a position where the hot section connection pipe is located between the low pressure safety injection pipe and the first electric isolation valve, and the other end is connected to the heat.
- the segment connecting pipe is located between the second electric isolation valve and the first circuit hot section of the reactor coolant system, so that the two check valves are simultaneously connected in parallel with the first electric isolation valve and the second electric isolation valve.
- the hot section safety injection pipe is provided with a check valve in parallel with the first electric isolation valve.
- one end of the hot section safety injection pipe is connected to the position of the hot section connecting pipe between the low pressure safety injection pipe and the first electric isolation valve. And the other end is connected at a position where the hot section connecting pipe is located between the first electric isolation valve and the second electric isolation valve, so that the check valve is connected in parallel with the first electric isolation valve.
- the hot section safety injection pipe is provided with a check valve in parallel with the second electric isolation valve.
- one end of the hot section safety injection pipe is connected to the hot section connecting pipe at a position between the first electric isolation valve and the second electric isolation valve, and the other end is connected.
- the position on the hot section connecting pipe is between the second electric isolation valve and the hot section of the first circuit of the reactor coolant system, so that the check valve is connected in parallel with the second electric isolation valve.
- the present invention separates the water intake function of the RHR hot section from the hot water injection function by setting a separate hot section safety injection pipeline; and injects the pipeline safely in a separate heat section.
- the check valve is arranged to realize the isolation from the primary circuit of the reactor coolant system under normal operating conditions. Since the check valve does not require manual operation by the operator after the accident, it is not necessary to configure the electrical system as the power source. The maintenance and maintenance costs are low, and the probability of safe injection success of the hot section after the accident is greatly improved, and the CDF (Core Damage Frequency) and the LRF value (Large Release Frequency) are effectively reduced.
- CDF Core Damage Frequency
- LRF value Large Release Frequency
- FIG. 1 is a schematic structural view of a first embodiment of a thermal injection safety injection system for a nuclear power plant according to the present invention.
- 2 is a schematic structural view of a second embodiment of a safety injection system for a thermal section of a nuclear power plant according to the present invention.
- 3 is a schematic structural view of a third embodiment of a thermal injection safety injection system for a nuclear power plant according to the present invention.
- a nuclear power plant hot section safety injection system 100 includes a hot section connecting duct 10 and a hot section safety injection duct 20, and one end of the hot section connecting duct 10 is connected to a low voltage.
- the safe injection conduit 30 is connected to the hot section 44 of the primary coolant circuit 40 of the reactor coolant system.
- the reactor coolant system primary circuit 40 includes a reactor core 41, a steam generator 42, a main pump 43, a heat section 44, a cold section 45, and a transition section 46, wherein the heat section 44 is coupled to the reactor core 41 and the steam generator 42. Between the cold section 45 is connected between the reactor core 41 and the main pump 43, and the transition section 46 is connected between the main pump 43 and the steam generator 42.
- the first electric isolation valve 101 and the second electric isolation valve 102 are spaced apart from each other in the hot section connecting pipe 10. In the position, the first electric isolation valve 101 is adjacent to the low pressure safety injection pipe 30, and the second electric isolation valve 102 is close to the reactor coolant.
- the hot section 44 of the primary circuit 40 of the system is close to the reactor coolant.
- the two ends of the hot section safety injection pipe 20 are respectively connected to the hot section connection pipe 10, and two check valves 201, 202 are provided thereon.
- one end of the hot section safety injection pipe 20 is connected at a position where the hot section connection pipe 10 is located between the low pressure safety injection pipe 30 and the first electric isolation valve 101, and the other end is connected to the hot section connection pipe 10 at the second electric isolation.
- the position between the valve 102 and the hot section 44 of the primary coolant circuit 40 of the reactor coolant system is such that the two check valves 201, 202 are simultaneously connected in parallel with the first electrically isolated valve 101 and the second electrically isolated valve 102.
- the present invention separates the RHR hot section water intake function from the hot section water injection function by providing a separate hot section safety injection pipe 20, so that the two do not affect each other; and by setting two stops on the separate hot section safety injection pipe 20.
- the return valves 201, 202 are used to isolate the primary coolant circuit 40 from the reactor coolant system under normal operating conditions. Since the two check valves 201, 202 do not require manual operation by the operator after an accident, there is no need to configure the electrical system as a power source. The source not only has the low cost of configuration, maintenance and overhaul, but also greatly increases the probability of successful safety injection of the hot section after the accident, effectively reducing the CDF and LRF values.
- a nuclear power plant hot section safety injection system 200 includes a hot section connecting duct 10 and a hot section safe injection duct 50, wherein the hot section connecting duct 10 One end is connected to a low pressure safety injection line 30 and the other end is connected to a hot section 44 of the reactor coolant system primary circuit 40.
- the hot section connection conduit 10 is spaced apart from a first electrically isolated valve 101 adjacent the low pressure safety injection conduit 30 and a second electrically isolated valve 102 adjacent the hot section 44 of the primary coolant 40 of the reactor coolant system.
- Both ends of the hot section safety injection pipe 50 are connected to the hot section connection pipe 10, respectively, and a check valve 501 is provided thereon.
- one end of the hot section safety injection pipe 50 is connected at a position where the hot section connection pipe 10 is located between the low pressure safety injection pipe 30 and the first electric isolation valve 101, and the other end is connected to the hot section connection pipe 10 at the first electric isolation.
- the position between the valve 101 and the second electric isolation valve 102 is such that the check valve 501 is connected in parallel with the first electric isolation valve 101.
- the operator when the hot spot injection function needs to be performed under the medium and large LOCA accident conditions, the operator does not need to manually open the first and second electric isolation valves 101 and 102 at the same time, but only needs to manually open the second electric motor.
- the isolation valve 102 is sufficient, so that the probability of successful injection of the hot section after the accident is also significantly improved.
- a nuclear power plant hot section safety injection system 300 includes a hot section connecting duct 10 and a hot section safe injection duct 60, wherein one end of the hot section connecting duct 10 is connected to a low voltage.
- the safety injection conduit 30 is connected to the hot section 44 of the primary coolant circuit 40 of the reactor coolant system.
- the hot section connection pipe 10 is spaced apart from the first electric isolation valve 101 adjacent to the low pressure safety injection line 30 and the second electric isolation valve 102 adjacent to the hot section 44 of the primary coolant circuit 40 of the reactor coolant system.
- the two ends of the hot section safety injection pipe 60 are respectively connected to the hot section connection pipe 10, and a check valve 601 is provided thereon.
- one end of the hot section safety injection pipe 60 is connected to the hot section connecting pipe 10 at a position between the first electric isolation valve 101 and the second electric isolation valve 102, and the other end is connected to the hot section connecting pipe 10 at the
- the position between the second electrically isolated valve 102 and the hot section 44 of the primary coolant circuit 40 of the reactor coolant system causes the check valve 601 to be in parallel with the second electrically isolated valve 102.
- the hot zone injection function needs to be performed under the medium and large LOCA accident conditions, It is not necessary for the operator to manually open the first and second electric isolation valves 101, 102 at the same time, but only the first electric isolation valve 101 needs to be manually opened, so that the probability of successful safety injection of the hot section after the accident is also significantly improved.
- the present invention can also be appropriately modified and modified as described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described herein, and modifications and variations of the present invention are intended to fall within the scope of the appended claims.
- the present invention is not limited to the specific embodiments disclosed and described herein, and modifications and variations of the present invention are intended to fall within the scope of the appended claims.
- some specific terms are used in the specification, these terms are merely for convenience of description and do not impose any limitation on the invention.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
Claims
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1513533.8A GB2524453B (en) | 2013-08-01 | 2013-11-24 | Safety injection system of a hot leg of a nuclear power station |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201320468424.1 | 2013-08-01 | ||
CN2013204684241U CN203366763U (en) | 2013-08-01 | 2013-08-01 | Safety injection system of hot leg of nuclear power station |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2015014047A1 true WO2015014047A1 (en) | 2015-02-05 |
Family
ID=49814494
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/CN2013/087741 WO2015014047A1 (en) | 2013-08-01 | 2013-11-24 | Safety injection system of hot leg of nuclear power station |
Country Status (3)
Country | Link |
---|---|
CN (1) | CN203366763U (en) |
GB (1) | GB2524453B (en) |
WO (1) | WO2015014047A1 (en) |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20090154635A1 (en) * | 2007-12-18 | 2009-06-18 | Korea Plant Service & Engineering Co., Ltd. | Drainage apparatus and drainage method for reactor coolant system |
CN101079333B (en) * | 2006-05-26 | 2010-07-14 | 中国核动力研究设计院 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
CN102034559B (en) * | 2010-09-19 | 2012-08-01 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
CN202948735U (en) * | 2012-12-03 | 2013-05-22 | 中核核电运行管理有限公司 | Structure for increasing inner pressure of blocked pipe section |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102867549B (en) * | 2012-09-27 | 2017-05-10 | 中国核电工程有限公司 | Reactor cavity water injection cooling system with combination of active and passive power |
-
2013
- 2013-08-01 CN CN2013204684241U patent/CN203366763U/en not_active Expired - Fee Related
- 2013-11-24 WO PCT/CN2013/087741 patent/WO2015014047A1/en active Application Filing
- 2013-11-24 GB GB1513533.8A patent/GB2524453B/en active Active
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN101079333B (en) * | 2006-05-26 | 2010-07-14 | 中国核动力研究设计院 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
US20090154635A1 (en) * | 2007-12-18 | 2009-06-18 | Korea Plant Service & Engineering Co., Ltd. | Drainage apparatus and drainage method for reactor coolant system |
CN102034559B (en) * | 2010-09-19 | 2012-08-01 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
CN202948735U (en) * | 2012-12-03 | 2013-05-22 | 中核核电运行管理有限公司 | Structure for increasing inner pressure of blocked pipe section |
Non-Patent Citations (2)
Title |
---|
HAO, XIANGWEI;: "Comparison and Analysis of the Safety Systems of AP1000 and M310", NEW TECHNOLOGY & NEW PRODUCTS OF CHINA, no. 6, 31 March 2012 (2012-03-31), pages 253 * |
YANG MING ET AL.: "Study on Quantitative Reliability Analysis by Multilevel Flow Models for Nuclear Power Plants", NUCLEAR POWER ENGINEERING, vol. 32, no. 4, 31 August 2011 (2011-08-31), pages 72 - 76 * |
Also Published As
Publication number | Publication date |
---|---|
CN203366763U (en) | 2013-12-25 |
GB2524453A (en) | 2015-09-23 |
GB2524453B (en) | 2020-06-17 |
GB201513533D0 (en) | 2015-09-16 |
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