GB2523949A - High-pressure safe injection system for nuclear power stations - Google Patents
High-pressure safe injection system for nuclear power stations Download PDFInfo
- Publication number
- GB2523949A GB2523949A GB1512027.2A GB201512027A GB2523949A GB 2523949 A GB2523949 A GB 2523949A GB 201512027 A GB201512027 A GB 201512027A GB 2523949 A GB2523949 A GB 2523949A
- Authority
- GB
- United Kingdom
- Prior art keywords
- injection
- boric acid
- pipeline
- reactor
- loop
- 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.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/033—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by an absorbent fluid
-
- 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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
-
- 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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- 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
A high-pressure safe injection system for nuclear power stations is configured on multiple loops (5) of a loop system of a reactor. The high-pressure safe injection system comprises at least one boric acid injection unit (15) and at least one coolant injection unit (16). The boric acid injection unit (15) comprises a concentrated boric acid injection box (8) and a concentrated boric acid injection pipeline (7). One end of the concentrated boric acid injection pipeline (7) is connected to the concentrated boric acid injection box (8), and the other end of the concentrated boric acid injection pipeline (7) penetrates into a containment vessel (11) and then is connected to a cold tube section (501) of a loop (5) of a loop system of the reactor. The coolant injection unit (16) comprises a water source (14) and a coolant injection pipeline (6) connected to the water source (14). The coolant injection pipeline (6) comprises a cold tube section injection pipeline (9) and a heat tube section injection pipeline (10) that are connected in parallel; the cold tube section injection pipeline (9) penetrates into the containment vessel (11) and then is connected to a cold tube section (501) of a loop (5) of a loop system of the reactor; and the heat tube section injection pipeline (10) penetrates into the containment vessel (11) and then is connected to a heat tube section (502) of a loop (5) of a loop system of the reactor. Multiple pipelines of the injection system are not mutually interfered, thereby facilitating flow control; and the injection system has high security.
Description
Specification
High-pressure Safe Injection System for Nuclear Power stations
Technical Field
The present invention relates to the field of pressurized water reactor (PWR) nuclear power stations, specifically to a high-pressure safe injection system for PWR nuclear power stations. Art
in pressurized water reactor nuclear power stations, the safe injection system o functions in implementing emergency core cooling in the event of fault of a primary coolant pipeline or main steam pipeline and it is one of the important engineered safety facilities. In previous desIgn. the high-pressure safe injeclion system uses two of three charging pumps of a chemical and volume control system as safe injecflon pumps. The injection flow of each safe injection pun.p is is gatIiercd*by a header mand 1d and then distributed to cold and hot pipe sections of each loop. In terms of such design, in the event of fault of a certain injection pipeline, it will aflèet the flow of other injection pipelines. High-pressure safe injection system is provided with just one concentrated boric acid injection box.
Only one injection pipeline passes the concentrated boric acid injection box to inject concentrated boric acid solution into a primary circuit system so as to maintain the core under subcritical state. In case of failure of this pipeline, this function can not he achieved, reducing the emergency cooling capacity of the safe injection system.
the invention The present invenl.ion aims to provide a safe injection system for nuclear power stations, which can independently inject cooling water to the primary s circuit system of the reactor, improvuig s stem reliability and enhancing the capability of. safe injection system in implerneth:ing emergency core cooling. it is separately provided with concentrated boric acid injection series, which can inject boric acid solution into the core in the condition of unsafe injection system operation so as to provide sufficient negative reactivity to achieve shutdown.
To solve the above technical problems, the technical solution of the present invention provides a highressure safe injection system thr nuclear power stations, which is configured on multiple loops of a primary circuit system, comprising at least one boric acid injection unit and at least one coolant injection unit; The boric acid injection unit comprises a concentrated boric acid injection box and a concentrated boric acid injection pipeline, wherein one end of the concentrated boric acid injection, pipeline i.s connected with the concentrated boric acid injection box and the other end of the concentrated boric acid injection pipeline penetrates into a containment vessel and then is connected to a cold pipe section of a loop of the primary circuit system of the reactor; The coolant injection unil comprises a water source and a coolant injection pipeline, wherein the coolant injection pipeline is connected with the water source; the coolant injection pipeline comprises a cold pipe section injection pipeline and a hot pipe section injection pipeline which are connected in parallel; the cold pipe section injection pipeline penetrates into the containment vessel and then is connected to a cold pipe section of a loop of the primary circuit system of the reactor; and the hot pipe section injection pipeline penetrates into the containment vessel and then is connected to a hot pipe section of a loop of the primary circuit system of the reactor.
The water source can be an in-vessel retbeling water storage tank.
The concentrated boric acid injection pipeline is provided with a boric acid to injection pump; and the coolant injection pipeline is provided with a high-pressure safe injection pump.
The primary circuit system of the reactor includes three loops.
The three loops are provided with four coolant injection units, two of the injection units are independently connected to a first loop and a second loop of the is three loops of the reactor, the cold pipe section injection pipelines of the other two coolant injection units are connected to the cold pipe sections of a third loop of the three loops of the reactor, and the hot pipe section injection pipelines of the other two coolant injection units are connected to the hot pipe sections of a third loop of the three loops of the reactor.
The three loops of the reactor are provided with two boric acid injection units, the cold pipe sections of the three 1oops are connected through a header manifold; the concentrated boric acid injection pipelines of the two boric acid -It-injection units are connected to the header manifold; concentrated boric acid injection pipelines of the two boric acid injection units are connected via a connection pipeline, and the connection pipeline is provided with an isolating valve.
The. beneficial effects oIthe present invention are as follows: (1) The multiple high.pressure safe injection pipelines respectively inject into hot and cold pipe sections of multiple loops of the primary circuit system, without interfering each other, which can facilitate the how regulation: (2) An independent boric acid injection system hi jccts concentrated boric acid into the primary circuit system after safe injection signal is sent out, and this funcrion does not rely on operation of highpressure sale injection pumps or related injection pipelines; (3) After shutdown signal is issued but the control rod can not he plugged in to shut down, the boric acid injection pump is automatically started to inject the high concentrated boric acid from the two boric acid injection boxes into the reactor core, resulting in enough negative reactivity to achieve shutdown, Fig. I is the schematic diagram of a loop of the primal)' circuit system of the reactor for nuclear power stations; Fig. 2 is the schematic diagram of the highpressure safe injection system.
nuclear power stations provided by the present invention; Fig. 3 is the Local schematic diagram A. of application of the highpressure safe injection, system far nuclear power stations provided by the present invention to a three-loop reactor; Fig. 4 is the local schematic diagram B of application of the high-pressure safe injection system for nuclear power stations provided by the present invention to a three-loop reactor; Fig. 5 is the local schematic diagram C of application of the high-pressure sale injection system ihr nuclear power stations provided by the present invention to a three-loop reactor; In the figures, 1 refers to reactor core, 2 refers to pressure vessel, 3 refers to steam generator, 4 refers to pump. S refers to ioop, 6 refers to coolant injection IC pipeline, 7 refers to concentrated acid injection pipeline, 8 refers to concentrated boric acid injection hex, 9 refers to cold pipe section injection pipeline, 10 re:ers to hot pipe section injection pipeline, 11 refers to containment vessel, 12 refers to boric acid injection pump. 13 refers to high-pressure safe injection pump. 14 refers to water source, 15 refers to boric acid injection unit, 14 refers to coolant in. jection is unit. 17 refers to isolating valve, 18 refers to connection pipeline, and 9 refers to header rnani fold, Embodiments The following drawings and embodiments are further description of the present invention in details.
The nuclear power station reactor comprises a primary circuit system, wherein the primary circuit system comprises three loops 5, one of which 5 is shown in Fig. 1; each loop comprises hot pipe sections 502 and cold pipe sections 501; the coolant is injected through a pump 4 from the coid pipe sections 501 into a pressure vessel 2, absorbs heat from a reactor core 1, leaves the pressure vessel 2, then passes the hot pipe sections 502 to release heat through a steam generator 3 and then returns to the cold pipe sections 501 again and finally is injected into the pressure vessel 2 to achieve the cycle; As shown in Fig. 2, the high-pressure safe injection system for nuclear power stations claimed in the present invention comprises at least one boric acid injection unit 15 and at least one coolant injection unit 16; The boric acid injection unit 15 comprises a concentrated boric acid injection box 8 and a concentrated boric acid injection pipeline 7, wherein one end of the concentrated boric acid injection pipeline 7 is connected with the bottom of the concentrated boric acid injection box 8 and the other end of the concentrated boric acid injection pipeline 7 penetrates into a containment vessel ii and then is connected to a cold pipe section 501 of a loop 5 of the primary circuit system of the reactor; and the concentrated boric acid injection pipeline 7 is provided with a boric acid injection pump 12; The coolant injection unit 16 comprises a water source 14 and a coolant injection pipeline 6, wherein the coolant injection pipeline 6 is connected with the water source 14; the coolant injection pipeline 6 comprises a cold pipe section injection pipeline 9 and a hot pipe section injection pipeline 10 which are connected in parallel; the cold pipe section injection pipeline 9 penetrates into the containment vessel 11 and then is connected to a cold pipe section 501 of a loop 5 of the primary circuit system of the reactor; and the hot pipe section injection pipeline 10 penetrates into the containment vessel 11 and then is connected to a hot pipe section 502 of a loop 6 of the primary circuit system of the reactor; the coolant injection pipeline 6 is provided with a high-pressure safe injection pump 13; and the water source 14 can be a ref kieling water storage tank in the containment vessel 11.
As shown in Fig. 3 and Fig. 4, the three loops 5 of the reactor are provided with four coolant injection units 16, two of the injection units 16 are independently connected to a first loop and a second loop of the three loops of the reactor, the cold pipe section injection pipelines 9 of the other two coolant injection units 16 are connected to the cold pipe sections 501 of a third loop of the three loops 5 of the reactox and the hot pipe section injection pipelines 10 of the other two coolant injection units 16 are connected to the hot pipe sections 502 of a third loop of the three loops 5 of the reactor.
As shown in Fig. 5, the three loops 5 of the reactor are provided with two boric acid injection units 15, the cold pipe sections 501 of the three loops 5 are connected through a header manifold 19; the concentrated boric acid injection pipelines 7 of the two boric acid injection units 15 are connected to the header manifold 19; the pipe sections between a high-pressure safe injection pump 13 and a concentrated boric acid box 8 on the concentrated boric acid injection pipelines 7 of the two boric acid injection units 15 are connected via a connection pipeline 18, and the connection pipeline 18 is provided with an isolating valve 17.
Specific process includes: (1) Safe injection process Upon receiving the safe injection signal, the following actions are immediately implemented: A) Starting four high-pressure safe injection pumps on four coolant injection units 16; B) Starting two boric acid injection pumps A and B; S In the safe injection stage, the reactor coolant pressure is decreased rapidly to inject the boron-containing water into the cold pipe section 501 of a loop 5 of the primary circuit system and then into the reactor core.
High-pressure safe injection pump 13 and boric acid injection pump 12 enable the reactor pressure vessel to be filled with water again and then submerge the reactor core again.
The simultaneous injection of cold pipe section 501 and the hot pipe section 502 ensures that the boron concentration of the core is lower than its solubility lint In the long-term safe injection stage, the safe injection system also injects into bot and cold pipe sections simultaneously until: A) The core cooling is completed; B) The environmental conditions (pressure, temperature and radiation level) allow entry into the containment vessel.
(2) Shutdown after concentrated boric acid injection In case of the need for shutdown but failure of the control rod, a boric acid injection subsystem is used as a second system for shutdown. When the reactor protection system sends out shutdown signal but the control rod can not be plugged in to shut down, boric acid injection pump 12 will be automatically started according to the logic treatment results of the shutdown signals and power range neutron fluence rate signals to inject high concentrated boron acid from two boric acid injection boxes 8 into the reactor core in order to introduce sufficient negative reactivity to achieve shutdown. In case of fitilure of one boric acid injection unit 15, the isolating valve 17 on the connection pipeline 18 can be opened so as to use an intact boric acid injection unit 15 to inject high concentrated boric acid solution into the cold pipe section 501 of the three loops of the primary circuit system to achieve shutdown.
Claims (6)
- Clalins 1. A high-pressure safe injection system for nuclear power stations, wherein it is configured on multiple loops of a primary circuit system of the reactor, and it comprises at least one boric acid injection unit and at least one coolant injection S unit; The boric acid injection unit comprises a concentrated boric acid injection box and a concentrated boric acid injection pipeline, wherein one end of the concentrated boric acid injection pipeline is connected with the concentrated boric acid injection box and the other end of the concentrated boric acid injection io pipeline penetrates into a containment vessel and then is connected to a cold pipe section of a loop of the primary circuit system of the reactor; The coolant injection unit comprises a water source and a coolant injection pipeline, wherein the coolant injection pipeline is connected with the water source; the coolant injection pipeline comprises a cold pipe section injection pipeline and a hot pipe section injection pipeline which are connected in parallel; the cold pipe section injection pipeline penetrates into the containment vessel and then is connected to a cold pipe section of a loop of the primary circuit system of the reactor; and the hot pipe section injection pipeline penetrates into the containment vessel and then is connected to a hot pipe section of a loop of the primary circuit system of the reactor.
- 2. The high-pressure safe injection system for nuclear power stations according to Claim 1, wherein the water source can be an in-vessel refueling water storage tank.
- 3. The high-pressure safe injection system for nuclear power stations according to Claim 1, wherein the concentrated boric acid injection pipeline is provided with a boric acid injection pump; and the coolant injection pipeline is provided with a high-pressure safe injection pump.
- 4. The high-pressure safe injection system for nuclear power stations according to Claim 1, wherein the primary circuit system of the reactor includes three loops.
- 5. The high-pressure safr injection system for nuclear power stations according to Claim 4, wherein the three loops are provided with four coolant injection units, two of the injection units are independently connected to a first loop and a second loop of the three loops of the reacto; the cold pipe section injection pipelines of the other two coolant injection units are connected to pipeline! and the cold pipe section of a third loop of the three loops of the reactor, and the hot pipe section injection pipelines of the other two coolant injection units are connected to pipeline I and the hot pipe section of a third loop of the three ioops of the reactor.
- 6. The high-pressure safe injection system for nuclear power stations according to Claim 4, wherein the three loops of the reactor are provided with two boric acid injection units, the cold pipe sections of the three loops are connected through a header manifold; the concentrated boric acid injection pipelines of the two boric acid injection units are connected to the header manifold; concentrated boric acid injection pipelines of the two boric acid injection units are connected via a connection pipeline, and the connection pipeline is provided with an isolating valve.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201210531614.3A CN103871506B (en) | 2012-12-11 | 2012-12-11 | A kind of nuclear power station high-pressure safe injection system |
PCT/CN2013/088601 WO2014090106A1 (en) | 2012-12-11 | 2013-12-05 | High-pressure safe injection system for nuclear power stations |
Publications (4)
Publication Number | Publication Date |
---|---|
GB201512027D0 GB201512027D0 (en) | 2015-08-19 |
GB2523949A true GB2523949A (en) | 2015-09-09 |
GB2523949A8 GB2523949A8 (en) | 2015-09-16 |
GB2523949B GB2523949B (en) | 2020-07-01 |
Family
ID=50909945
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1512027.2A Active GB2523949B (en) | 2012-12-11 | 2013-12-05 | High-pressure safe injection system for nuclear power stations |
Country Status (5)
Country | Link |
---|---|
CN (1) | CN103871506B (en) |
AR (1) | AR093899A1 (en) |
GB (1) | GB2523949B (en) |
WO (1) | WO2014090106A1 (en) |
ZA (1) | ZA201504982B (en) |
Families Citing this family (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN105244062B (en) * | 2014-07-09 | 2017-07-14 | 国核华清(北京)核电技术研发中心有限公司 | Passive pressure accumulation safety injection system and passive pressure accumulation pacify injecting method |
CN104616707B (en) * | 2014-12-30 | 2017-03-22 | 中国原子能科学研究院 | Boron injection system for second reactor shutdown system of research reactor |
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 |
CN109147967B (en) * | 2017-06-15 | 2022-08-16 | 广东核电合营有限公司 | Boron concentration control device and method for nuclear power station |
CN108091407B (en) * | 2017-11-10 | 2019-11-15 | 中广核研究院有限公司 | High-pressure injection system and its Safety Injection method |
CN107816431B (en) * | 2017-11-23 | 2024-06-04 | 山东省农业机械科学研究院 | Nuclear second-level high-pressure safety injection pump environment simulation test system |
CN109300556B (en) * | 2018-09-19 | 2024-06-18 | 中广核研究院有限公司 | Reactor steady voltage system with safety notes function |
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 |
CN109859866B (en) * | 2019-03-06 | 2022-02-22 | 中国核动力研究设计院 | Method for relieving accident consequence of main steam pipeline rupture |
CN110580957B (en) * | 2019-09-19 | 2021-04-06 | 中国核动力研究设计院 | Reactor charging starting method without external neutron source |
CN111128410B (en) * | 2019-12-31 | 2022-07-26 | 中国核动力研究设计院 | Heat pipe reactor system and energy conversion mode thereof |
CN115237046A (en) * | 2022-07-21 | 2022-10-25 | 中国核动力研究设计院 | Manual prohibition method and device for safety injection signal, terminal and readable storage medium |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5178821A (en) * | 1991-06-13 | 1993-01-12 | General Electric Company | Standby passive injection coolant water safety injection system for nuclear reactor plants |
CN201699776U (en) * | 2010-05-20 | 2011-01-05 | 王珍珍 | Multifunctional telephone |
CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
CN101847451B (en) * | 2009-06-19 | 2012-10-31 | 中广核工程有限公司 | Safety injection system |
CN203026166U (en) * | 2012-12-11 | 2013-06-26 | 中国核动力研究设计院 | High-pressure safe injection system for nuclear power stations |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE795482A (en) * | 1972-02-19 | 1973-05-29 | Siemens Ag | NUCLEAR REACTOR COOLING SYSTEM |
DE2316066C2 (en) * | 1973-03-30 | 1982-05-27 | Siemens AG, 1000 Berlin und 8000 München | Nuclear reactor, especially pressurized water reactor |
US4181570A (en) * | 1976-03-17 | 1980-01-01 | Combustion Engineering, Inc. | Post-LOCA core flushing system |
JPH06201880A (en) * | 1993-01-06 | 1994-07-22 | Toshiba Corp | Boric acid flowout prevention device |
-
2012
- 2012-12-11 CN CN201210531614.3A patent/CN103871506B/en active Active
-
2013
- 2013-12-05 GB GB1512027.2A patent/GB2523949B/en active Active
- 2013-12-05 WO PCT/CN2013/088601 patent/WO2014090106A1/en active Application Filing
- 2013-12-10 AR ARP130104606A patent/AR093899A1/en active IP Right Grant
-
2015
- 2015-07-10 ZA ZA2015/04982A patent/ZA201504982B/en unknown
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5178821A (en) * | 1991-06-13 | 1993-01-12 | General Electric Company | Standby passive injection coolant water safety injection system for nuclear reactor plants |
CN101847451B (en) * | 2009-06-19 | 2012-10-31 | 中广核工程有限公司 | Safety injection system |
CN201699776U (en) * | 2010-05-20 | 2011-01-05 | 王珍珍 | Multifunctional telephone |
CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
CN203026166U (en) * | 2012-12-11 | 2013-06-26 | 中国核动力研究设计院 | High-pressure safe injection system for nuclear power stations |
Non-Patent Citations (1)
Title |
---|
Journal of the Shanghai University of Electric Power Vol. 27, No. 6, December 2011, Qian Hong et al, "Analysis and Simulation for Passive Safety Reactor Coolant System of the AP1000", pages 544-548 * |
Also Published As
Publication number | Publication date |
---|---|
ZA201504982B (en) | 2016-12-21 |
AR093899A1 (en) | 2015-06-24 |
WO2014090106A1 (en) | 2014-06-19 |
GB2523949B (en) | 2020-07-01 |
GB2523949A8 (en) | 2015-09-16 |
CN103871506B (en) | 2016-12-21 |
GB201512027D0 (en) | 2015-08-19 |
CN103871506A (en) | 2014-06-18 |
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