GB2520215A - Water flooding system for cooling nuclear power plant reactor cavity - Google Patents
Water flooding system for cooling nuclear power plant reactor cavity Download PDFInfo
- Publication number
- GB2520215A GB2520215A GB1504123.9A GB201504123A GB2520215A GB 2520215 A GB2520215 A GB 2520215A GB 201504123 A GB201504123 A GB 201504123A GB 2520215 A GB2520215 A GB 2520215A
- Authority
- GB
- United Kingdom
- Prior art keywords
- water injection
- pipe
- standby
- water
- reactor cavity
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 264
- 238000001816 cooling Methods 0.000 title claims abstract description 23
- 238000002347 injection Methods 0.000 claims description 161
- 239000007924 injection Substances 0.000 claims description 161
- 241000282860 Procaviidae Species 0.000 claims 1
- 238000002955 isolation Methods 0.000 abstract 3
- 230000004888 barrier function Effects 0.000 abstract 2
- 238000009413 insulation Methods 0.000 abstract 2
- 238000011144 upstream manufacturing Methods 0.000 abstract 1
- 239000007921 spray Substances 0.000 description 9
- 239000000498 cooling water Substances 0.000 description 5
- 238000002844 melting Methods 0.000 description 4
- 230000008018 melting Effects 0.000 description 4
- 238000000034 method Methods 0.000 description 4
- 241001062472 Stokellia anisodon Species 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 230000014759 maintenance of location Effects 0.000 description 2
- PZZOEXPDTYIBPI-UHFFFAOYSA-N 2-[[2-(4-hydroxyphenyl)ethylamino]methyl]-3,4-dihydro-2H-naphthalen-1-one Chemical compound C1=CC(O)=CC=C1CCNCC1C(=O)C2=CC=CC=C2CC1 PZZOEXPDTYIBPI-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000005507 spraying Methods 0.000 description 1
Classifications
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- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- 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
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
-
- 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
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to a water flooding system for cooling a nuclear power plant reactor cavity, comprising a reactor cavity disposed in a reactor containment casing, a pressure container disposed in the reactor cavity, and a heat insulation barrier located between the reactor cavity and the pressure container and enclosing the pressure container, and further comprising an external water flooding system and an elevated water flooding system disposed in the containment casing; the external water flooding system comprises an external water source, an external water flooding pipe connected with the external water source, a reactor cavity water flooding pump disposed on the external water flooding pipe, and a first isolation valve and a second isolation valve respectively disposed at the upstream and downstream of the reactor cavity water flooding pump; the external water flooding pipe penetrates through the containment casing to connect to the bottom of the heat insulation barrier; the elevated water flooding system comprises an elevated water flooding tank, an elevated water flooding pipe connected with the external water flooding pipe and the bottom of the elevated water flooding tank, and a third isolation valve disposed on the elevated water flooding pipe. The present invention has a stable and reliable performance, can effectively relieve the consequences of a serious accident, and ensure the integrity of a reactor pressure container in a serious accident.
Description
Specification
A Water flooding System for Cooling A Nuclear Power P'ant Reactor Cavity
Technical Field of the invention
The utility model discloses a cooling system which refers to a water injection and cooling system of reactor cavity. flt is able to respond to and afleviate the accident of nuclear power plant.
Background of the Invention
Currently, numerous measures are adopted in the international arena to alleviate serious accident of PWR (pressurized water reactor) nuclear power plant; rather new technology of smelt retention measures in the reactor (IV K) is adopted to setde serious accident of reactor core inching in the power lant, it rcftrs to art alleviatEou method to serious accident in the nuclear power pl.an.t and undergoes the.fbliowing process: In case at' serious accidenL of reactor core melting in PWR (pressurized water reactor) nuclear power plant (station). 0001 down the outer space of reactor pressure vessel, lead out reactor heat, realize retention of smelt in the reactor core and assure the completeness of reactor pressure vessel. The said technology is already applied in USA AP600!1000 reactor to alleviate the serious accident, The design features are as follows: Upon occurrence of serious accident, the water in the refueling water tank of safety casing is adopted as the cooling water and injected into the reactor cavity passively through gravity; it sinks the lower head of reactor pressure vessel and cylinder a.t a certain height; the cooling water flows through runner between the reactor pressure vessel and heat conservation layer and cools down the outer wail of pressure vessel; upon heating and production of steam, it returns to the space of safety casing through hole in the upper part. of heat conservation layer. The design defect lies in only one "passive" cooling method (injection sinking), rather small water injection flow and low efficiency in heat exchange; besides, it lacks effective cooling of the cooling water and fails to assure heat exchange effect in the late operation period of system.
The utility model aims to settle the followin.g technical problem: In case of serious accident of reactor core melting in the nuclear power pant, it is able to adopt "active" and "passive" cooling water injection methods to cool down outer waIl of reactor pressure vesseL retain smelt of reactor core in the reactor pressure vessel and thus prevent water injection and cooling system of reactor cavity that may threaten the completeness of safety casing.
The technical plan of this utility model is designed to settle the said technical problem: The utility model discloses a water flooding system for cooling a nuclear power plant reactor cavity and consists of the reactor cavity in the safety casing, pressure vessel in the reactor cavity, heat shield surrounding the pressure vessd and between reactor cavity and pressure vessel, water injection system at the outside and high-level water injection system in the safety casing.
The said water injection system at the outside consists of the water source at the outside, outside water injection pipe connected with outside water source and water injection pump of reactor cavity in the outside water injection pipe; the outside water injection pipe penetrates through the safety casing and connects with the bottom part of heat shield.
The said high-level water injection system consists of the high-level water injection tank and high-level water injection pipe connected with bottom and outside water injection pipes of high4evel water injection tank.
The outside water source comes from the fire-f.ghting water source at the outer side of safety casing.
ft af so consists of No, 1 isolating valve and No. 2 isolating valve in the upper and lower reaches of water injection pump of reactor cavity as well as No, 3 isolating valve in the high-level water injecton pipe.
It also consists of the heat exchanger at the outer side of safety casing, No. 4 isolating valve between water ircc1ion pump of reaclor cavity and No. I isolating valve, heat exchange and water outlet pipe of outside water injection pipe between water injection pump of reactor cavity and No. 4 isolating valve and heat exchange and water inlet pipe of outside water injection pipe between No. 1 isolating valve and No. 4 isolating valve. The said heat exchange and water outlet pipe and heat exchange and water inlet pipe are connected with the water inlet and water outlet respectively.
It also consists of No. 1 standby pipe which is collocated with No. 1 standby isolating valve and standby water injection pump of reactor cavity from upper to lower reaches in sequence. No, I standby pipe is connected with the outside water injection pipe connecting No. I isolating valve and water injection pump of reactor cavity in a parallef manner.
S ft also consists of the standby heat exchanger at the outer side of safety casing, No. 2 standby isolating valve between standby water injection pump of reactor cavity and No. standby isolating valve, standby heat exchange and water outlet pipe in No, I standby pipe between standby water injection, pump of reactor cavity and No. 2 standby isolating valve and standby heat exchange and water inlet pipe in No. 1 standby pipe between No. I standby isolating valve and No. 2 standby isolating valve. The said standby heat exchange and water outlet pipe and standby heat exchange and water inlet pipe are connected with the water hdet and water outlet respectively.
It also consists of the low4ev& water injection system. The said low-level water injection system consists of the low-level water injection tank at the bottom of safety easing, low-level water injection pipe connected with the bottom of low-level water injection tank and No. 5 isolating valve of low-level water injection pipe. The low-*iev& main water pipe is connected with the outside water injection pipe between water injection pump of reactor cavity and No. 2 isolating valve..
It also consists of No, 2, standby pipe. No.3 standby isolating valve is coilocated in the said No. 2 standby pipe; one end of No. 2 standby pipe is connected with the bottom of low-level water injection tank while the other end is connected with No. 1 standby pipe in the t.tpper reaches of standby water injection pump of reactor cavity.
The check valve is collocated in the fire-fighting pipe between No. 2 isdating valve and "low-level water injection pipo outside water injection pipe" contact; check valve is coilocated in the outside water injection pipe between No. 1 isolating valve of safety casing and. "high-level water injection pipe-outside water injection pipe" contact; check valve is collocated i.n the high-level water injection pipe between No. 4 isolating valve and "hghlevei water iniection pipe outside water injection pipe" contact; check valve i.s coilocated in the low-level water injection pipe between No. 5 isolating valve and "low-level water injection pipe outside water injection pipe" contact; check valve is collocated in the lower reaches of No, 3 standby isolating valve in No, 2 standby pipe.
The heat shield is supported inside the reactor cavity; an empty cavity is produced between the said heat shield and pressure vessel, The exhaust window is collocated in the connection between empty cavity and top of reactor cavity. The horizontal level of exhaust window is higher than the low-level water iiection tank.
The beneficial effect of utility model is as follows: The system adopts "active" and "passive" water injection methods to assure stable and reliable properties; it is able to effectivefly alleviate the serious accident and assure the completeness of reactor pressure vessel in the serious accident.
ritionofDraws Fig, I refers to the schematic diagram of water injection and cooling system of reactor cavity in PWR (pressurized water reactor) nuclear power plant.
ID in the Fig: i-Pressure vessel; 2--Heat shield; 3 Low-level water injection tank; 4-High-level water in.ection tank; 5-'-No. 5 isolating vafte; 50l-No. 3 standby isolating valve; 6-Check valve; 7-Water injection pump of reactor cavity; S No, 4 isolating valve; 801-No. 2 standby isolating valve; 9 No. isolating valve; 901-No. 1 standby isolating valve; No. 2 isolating valve; ii' No. 3 isolating valve 12-Safety casing of reactor; 13- 1 5 Reactor cavity; 14-Outside water source; 15-Outside water injection pipe; 16 High-level water injection pipe; 1? Low-level water injection pipe; I 8-No, I standby pipe; 19-No. 2 standby pipe; 20-Exhaust window.
We wouid like to tIrther describe the utility model according to Fig. I and embodiment.
As shown in Fig. 1, the utility model discloses a water injection and cooling system of reactor cavity in PWR (pressurized water reactor) nuclear power plant. Reactor cavity 13 is collocated in the safety casing 1.2 of reactor; pressure vessel I is eollocated in the reactor cavity 13; the heat shield 2 is collocated between the reactor cavity 13 and pressure vessel I and surrounds the pressure vessel. 1; the high-level water injection system is coliocated in the safety casing 12; the structure of heat shield 2 can follow widely known AP 1000 design plan; the heat shield 2 is supported inside the reactor cavity 13; an etnoty cavity is produced with the pressure vessel. Exhaust window 20 is eolloeated between the said ern.pt cavity and top of reactor cavity.
The water injection system at the outside is collocated in the water injection and cooling system of reactor cavity. The said water injection system at the outside consists of the water source at the outside 14, outside water injection pipe IS connected with outside water source 14 and water injection pump 7 of reactor cavity in the outside water injection pipe 15; No. I isolating valve 9 and No 2 isolating valve 10 are coilocated in the upper and lower reaches of water injection pump 7 of reactor cavity; the outside water injection pipe 15 penetrates throu the safety casing 12, enters into the reactor cavity 13 and connects with the bottom part of heat shield 2. The said outside water source 14 can come from the fire-fighting water source outside the safety easing.
The high-level water injection system consists of the high-level water injection tank. 4 higher than the reactor core, high-level water injection pipe 16 connected. with bottom of high-level water injection tank 4 and highievel water injection pipe 16 in the outside water injection pipe 15 of safety easing 12 and No. 3 isolating valve 11 in the high-level water injection pipe 16. The said No. 3 isolating valve ii may refer to an isolating valve composed of two or above wo parallel isolating valves.
The heat exchanger is collocated at the outer side of safety casing 12; No. 4 isolating valve 8 is coilocated in the outside water iniection pipe 1 5 between water injection pump 7 of reactor cavity and No. 1 isolating valve 9: one end of heat exchange and water outlet pipe is connected with the outside water injection pipe 15 between water injection pump 7 of reactor cavity and Nt), 4 solating vave 8; one end of heat exchange and water inlet pipe is connected with the outside water injection pipe 15 between the said No. 1 isolating valve 9 and No, 4 isolating valve 8. The other ends of said heat exchange and water outlet pipe and heat exchange and water inlet pipe are connected with the water inlet and water outlet respectively.
It also consists of' the lowievel water injection system. The said low-level water injecon system consists of the low-level water injection tank 3 at the bottom of safety casing, low-level water injection pipe 17 connected with the bottom of lowievel water injection tank 3 and No. S isolating valve 5 of low-level water injection pipe 17, The low-level water injection pipe 17 is connected with the outside water injection pipe 15 between water injection pump 7 of reactor cavity and No. 2 isolating valve 10.
The check valve 5 is collocated in the outside water injection pipe 15 between No. 2 isolating valve 10 and "low-level water injection pipe 17 outside water injection pipe 15" contact; check valve 6 is collocated in the outside water injection pipe 15 between No. 1 isolating valve 9 of safety casing 12 and "high-level water injection pipe 16-outside water injection pipe 15" contact; check valve 6 is coilocated in the high-level water injection pipe 16 between No, 4 isolating valve ii and "high-level water injection pipe 16-outside water injection pipe 15" contact; check valve 6 is collocated in the low-level water injection pipe 1 7 between No, 5 isolating valve 5 and "low-level water injection pipe 17-outside water injection pipe 15" contact.
In No. 1 standby pipe 18, No, I standby isolating valve 901 and standby water injection pump 701 of reactor cavity are coliocated from upper to lower reaches in sequence; No. I standby pipe 18 is connected with the outside water injection pipe 15 between No. I isolating vaMve 9 and water injection pump 7 of reactor cavity in a parallel manner. That is to say. one end is connected with the lower reaches of No. 1 isolating valve 9 and the other end is cormected with the check valve 6 between water injection pump 7 of reactor cavity and lower reaches of No. 2 isolating valve 10.
it also consists of the standby heat exchanger at the outer side of safety easing 12; No. 2 standby isolating valve 80! is coilocated between standby water injection pump 701 of reactor cavity and No. 1 standby isolating vaLve 901; one end of the standby heat exchange and water ouflet pipe is connected with No. 1 standby pipe between standby water injection pump 701 of reactor cavity and No. 2 standby isolating valve 801; one end of the standby heat exchange and water inlet pipe is connected with No. I standby pipe IS between No. l standby isolating valve 901 and No, 2 standby isolating valve 801. The other ends of said standby heat exchange and water outlet pipe and standby heat exchange and water inet pipe are connected with the water inlet and water outlet respectively.
It also consists of No. 2 standby pipe 19 whose end is connected with the bottom of low level water injection tank) while the other end is connected with No, I standby pipe 18 in the upper reaches of standby water injection pump 701 of reactor cavity. No. 3 standby isolating valve 501 is coliocated in No, 2 standby pipe 19. Check valve is coliocated in the lower reaches of No. 3 standby isolating valve 501 in No. 2 standby pipe 19.
Spray pipe is connected with the ower reaches of No, 5 isolating valve in the low4cvci water injection pipe 17. One end of the spray pipe is connected with the spray system of safety easing; the spray pipe executes spraying to the safety casing as a bypass pipe under the accident. At the same time, the standby spray pipe is connected with the lower reaches of No. 3 standby isolating valve 501 in No, 2 standby pipe 19; the other end of standby spray pipe is connected with the spray system of safety casing. The standby spray pipe serves for contingency.
The horizontal level of exhaust window 20 in the utility model is higher than the low level water injection tank).
Under the normal operation of unit and designed datum accident of the unit, the water injection and cooling system of reactor cavity is isolated and idled. In case of serious accident which leads to melting of reactor core, the operator will manually operate the system.
In case of serious accident which leads to melting of reactor core, the water injection and coohng system of reactor cavity is operated. The operator manually opens No. 1 isolating valve 9, No. 4 isolating valve 8 and No. 5 isolating valve 5 according to the temperature sial at the outlet of reactor core; starts the water injection pump 7 of reactor cavity, takes water from the lowievel water injection tank 3 and fills water between the outer wal! of reactor pressure vessel i and heat shield 2; cools down the outer wall of reactor pressure vessel 1; flows cooled water back to the low-level water injection tank 3 through said exhaust window 20 for circulation.
In the normal operation of system, the cooling water is heated and temperature is increased constantly; the operator can manually open the heat exchange and water outlet pipe and heat exchange and water inset pipe connected with heat exchanger in the water injection and cooling system. The heat exchanger can he coflocated for the spray system of safety casing; the operator closes No. 4 isolating valve 8 of outside water injection pipe 15; coo!s down waxer of low-level water injection tank 3 through heat exchanger and then fills into the reactor cavity 1 3; the outside water source 14 coordinates with the low-level water injection tank 3 to fill water into the reactor cavity 13; specifically, if the low-level water injection tank 3 fails or low-kvel water injection pipe 17 or No. 2 standby pipe 19 fails, the operator closes No. 5 isolating valve 5 and No. 3 standby isoating valve 501, opens No. 2 isolating valve 10 and makes use of the outside water source 14 to fill water into the reactor cavity 13.
If the unit loses total power supply, the operator opens No.3 isolating va've 1.1 of high-level water iniection pipe 16 at the lower end of high-level water injection tank 4 in the safdty casing; fills water in the high-level water injection tank 4 into the reactor cavity 13 through gravity and outside water injection, pipe 15; sinks the reactor cavity 13 to a certain height and realizes sustainable sinking of reactor cavity 13 and sustainable cooling of the outer wail of reactor pressure vessel I. a Claim
Claims (10)
- I. The utility model discloses a water flooding system for coohng a nuclear power plant reactor cavity and consists of the reactor cavity in the safety casing, pressure vessel in the reactor cavty, heat shield surrounding the pressure vessel and between reactor cavity arid pressure vesseL It is featured as ibliows: it also consists of the water injection system at the outside and high4cvel water injection system in the safety casing.The said water injection svstcn at the outside consists of the water source at the outside outside water injection pipe connected with outside water source and water inection pump of reactor cavity in the outside water injection pipe; the outside water injection pipe penetrates through the safty casing and connects with the bottom part of heat shield.The said highievel water injection system consists of the high-level water injection tank and high4evel water injection pipe connected with bottom and outside water injection pipes ofhigh1evei water injection tank.
- 2. The a waLer flooding system for cooling a nuclear power plant reactor cavity is coilocated according to cEahn 1.. It is featured as* *f()i].c)vs: The outside water source conies from the fire4ighting water source at the outer side of safety casing.
- 3. The a water flooding system fbr cooling a nuclear power plant reactor cavity is collocated according to claim 1. It is featured as follows: it also consists of No. 1 isolating valve and No, 2 isolating valve in the upper and lower reaches of water injection pump of reactor cavity as well as No. 3 isolating valve in the high-level water injection pipe.
- 4. The a water flooding system for cooling a nuclear power plant reactor cavity is collocated according to claim 3, it is featured as foflows: It also consists of th.e heat exchanger at the outer side of safety casing> No, 4 isolating valve between water injection pump of reactor cavity and No. 1 isolating valve, heat exchange and water out! ct pipe of outside water injection pipe between water injection pump of reactor cavity and 4 isolating valve and heat exchange and water inlet pipe of outside water injection pipe between No, I isolating valve and No. 4 isolating valve, The said heat exchange and water outlet pipe and heat exchange and water inlet pipe are connected with the water inlet and water outlet respectively.
- 5. The a water flooding system for cooling a nuclear power plant reactor cavity is coilocated according to claim I. It is featured as follows: Ii also consists of No. 1 standby pipe which is collocated with No. 1 standby isolating valve and standby water injection pump of reactor cavity from upper to lower reaches in sequence. No, 1 standby pipe Es connected with the outside water injection pipe connecting No. I isolating valve and waler injection pump of reactor cavity in a parallel maimer.
- 6. The a. water flooding system for cooling a nuclear power plant reactor cavity is coilocated according to claim 5. It is featured as follows: It also consists of the standby heat exchanger at the outer side of safety casing, No. 2 standby isolating valve between standby water injection pump of reactor cavity and No. I standby iso!ating valve, standby heat exchange and water outlet pipe in No, 1 standby pipe between standby water injection pump of reactor cavity and No. 2 standby isolating vifive and standby heat exchange and water inlet pipe in No. I standby pipe between No. I standby isolating valve and No. 2 standby isolating valve. The said standby heat exchange and water outlet pipe and standby heat exchange and.water inlet pipe are connected with the water inlet and water outlet respectively.
- 7. The a water flooding system for cooling a nuclear power plant reactor cavity is collocated according to claim 6. It is featured as follows: It also consists of the low-level water injection system. The said low-level water injection system consists of the low-level water injection tank at the bottom of safety casing, lowievel water irnection pipe connected with the bottom of low-level water injection tank and No. 5 isolatin.g valve of low-level water injection pipe. The low-level main water pipe is connected with the outside water injection pipe between water injection pump of reactor cavity and No. 2 isolating valve.
- 8. The a water flooding system for cooling a nuclear power plant reactor cavity is collocated according to claim 7. It is featured as follows: it also consists of No. 2 standby pipe.No. 3 standby isolating valve is collocated in the said No, 2 standby pipe; one end of No. 2 standby pipe is connected with the bottom of low-level water injection tank while the other end is connected with No. I standby pipe in the upper reaches of standby water injection pump of reactor cavity.
- 9. The a water flooding system for cooling a nucicar power plant reactor cavity is coliocated according to claim 8. It is featured as follows: The cheek valve i.s coltocated in the tire-fighting pipe between No. 2 isolating valve and "low-level water injection pipc-outside water injection pipe" contact; check valve is coliocated in the outside water injection pipe between No, 1 isolating valve of safety casing and "high-level water injection pipe-outside water injection pipe" contact; check valve is coliocated in the high-level water injection pipe between No. 4 isolating valve and "high-level water injection pipe-'-'outside water injection pipe" contact; check valve is collocated in the low-level water injection pipe between No. 5 isolating valve and "low-level water injection pipe outside water injection pipe" contact; S check valve is collocated. in the lower reaches of No. 3 standby isolating valve in No. 2 standby pipe.
- 10. l'he a water flooding system for cooling a nuclear power plant reactor cavity is collocated according to claim 1. It is featured as follows: The heat shield is supported inside the reactor cavity; an empty cavity is produced between the said heat shield and pressure vessel. The exhaust window is collocated in the connection between empty cavity and top of reactor cavity. The horizontzd level of exhaust window is higher than the iow'level water injection Lank.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210295150.0A CN103632736B (en) | 2012-08-20 | 2012-08-20 | A kind of nuclear power station Reactor cavity flooding cooling system |
| PCT/CN2013/081727 WO2014029305A1 (en) | 2012-08-20 | 2013-08-19 | Water flooding system for cooling nuclear power plant reactor cavity |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| GB201504123D0 GB201504123D0 (en) | 2015-04-22 |
| GB2520215A true GB2520215A (en) | 2015-05-13 |
| GB2520215B GB2520215B (en) | 2018-04-18 |
Family
ID=50149432
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1504123.9A Active GB2520215B (en) | 2012-08-20 | 2013-08-19 | A water flooding system for cooling a nuclear power plant reactor cavity |
Country Status (3)
| Country | Link |
|---|---|
| CN (1) | CN103632736B (en) |
| GB (1) | GB2520215B (en) |
| WO (1) | WO2014029305A1 (en) |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104183285B (en) * | 2014-08-12 | 2017-11-24 | 中国核电工程有限公司 | Cooling system outside a kind of reactor pressure vessel |
| CN105741887B (en) * | 2014-12-11 | 2017-11-14 | 中广核工程有限公司 | The passive Reactor cavity flooding system and method for nuclear power station |
| CN105895172A (en) * | 2014-12-26 | 2016-08-24 | 姚明勤 | Quick and effective design measure for passive safety of pressurized water reactor |
| CN104766637B (en) * | 2015-04-01 | 2017-03-29 | 中广核研究院有限公司 | Safety Injection integrated system |
| CN105047235B (en) * | 2015-06-09 | 2017-12-29 | 中国核动力研究设计院 | It is detained passive cooling system under nuclear reactor major accident state in fused mass heap |
| CN106803436B (en) * | 2015-11-26 | 2018-08-17 | 大亚湾核电运营管理有限责任公司 | The verification method and device of nuclear power plant's standby accident mitigation power supply accident application function |
| CN107945891B (en) * | 2017-10-19 | 2021-01-19 | 中国核电工程有限公司 | System with reactor core melt in-reactor detention and out-of-reactor detention functions |
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Also Published As
| Publication number | Publication date |
|---|---|
| GB2520215B (en) | 2018-04-18 |
| WO2014029305A1 (en) | 2014-02-27 |
| CN103632736A (en) | 2014-03-12 |
| CN103632736B (en) | 2016-08-10 |
| GB201504123D0 (en) | 2015-04-22 |
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