CN112967824A - Passive residual heat removal system for underwater nuclear power unmanned underwater vehicle - Google Patents
Passive residual heat removal system for underwater nuclear power unmanned underwater vehicle Download PDFInfo
- Publication number
- CN112967824A CN112967824A CN202110158816.7A CN202110158816A CN112967824A CN 112967824 A CN112967824 A CN 112967824A CN 202110158816 A CN202110158816 A CN 202110158816A CN 112967824 A CN112967824 A CN 112967824A
- Authority
- CN
- China
- Prior art keywords
- heat
- removal system
- underwater
- residual heat
- nuclear power
- 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
- 239000002918 waste heat Substances 0.000 claims abstract description 31
- 238000009413 insulation Methods 0.000 claims abstract description 21
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 24
- 238000009835 boiling Methods 0.000 claims description 8
- 239000007789 gas Substances 0.000 claims description 7
- 238000004321 preservation Methods 0.000 claims description 5
- 239000012774 insulation material Substances 0.000 claims description 3
- 238000012546 transfer Methods 0.000 description 9
- 238000007599 discharging Methods 0.000 description 8
- 239000013535 sea water Substances 0.000 description 8
- 239000000498 cooling water Substances 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- 239000002826 coolant Substances 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 239000010908 plant waste Substances 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
Images
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
-
- 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
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a passive residual heat removal system for an undersea nuclear power unmanned underwater vehicle, which comprises: a thermal insulation and a waste heat removal chamber; the heat insulation piece is sleeved on the outer surface of each heat pipe in the heat pipe bundle of the reactor; the waste heat discharge cavity is sleeved on the periphery of the heat pipe bundle, an outlet and an inlet are respectively arranged on the upper portion and the lower portion of the waste heat discharge cavity, a lower valve is installed at the inlet, and an upper valve is installed at the outlet. The passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle disclosed by the invention can continuously remove the reactor core residual heat without the need of an external power supply for providing power.
Description
Technical Field
The invention belongs to the field of nuclear energy, and particularly relates to a passive waste heat discharge system of an unmanned underwater vehicle.
Background
The nuclear power unmanned underwater vehicle is an ideal power device for deep sea development equipment due to the advantages of high energy density, long service life, independence of air and the like, and generally adopts a nuclear reactor to provide power for the underwater nuclear power unmanned underwater vehicle.
The discharge of the residual heat of the nuclear reactor is an important issue for ensuring the safety of the reactor. When the reactor takes place the loss of heat trap accident the reactor must be shut down, opens waste heat discharge system simultaneously and discharges the decay waste heat to ensure that the reactor core does not receive the damage, however, the reactor lasts the existence certain difficulty of discharging the decay waste heat after taking place the loss of heat trap accident, mainly reflects in: 1. because the external water source such as seawater can not be directly contacted with the reactor core, the heat in the reactor core can not be discharged in time, because the radioactive substances in the reactor core can be leaked and diffused to the outside if the external water source is directly contacted with and cools the reactor core, and the structure in the reactor core can be damaged due to the direct contact of the external water source such as seawater, which has certain corrosivity; 2. if the reactor is cooled only at the periphery, the heat of the central part in the reactor core is difficult to be led out, and the phenomenon of local overheating in the reactor core can occur, so that part of reactor core components are melted; 3. after the reactor breaks down, the whole power source is cut off, and the unmanned underwater vehicle is limited by underwater precious space resources in the cabin and is difficult to carry a diesel engine or a large storage battery pack, so that the waste heat cannot be discharged in an active mode.
At present, foreign military nuclear submarines generally adopt a traditional nuclear power plant active residual heat removal system, and the system respectively drives a main coolant, secondary side water supply of a steam generator and cooling water to perform forced circulation through a main coolant pump, a residual heat removal pump or a cooling water pump and other equipment under the condition of external power supply (such as a large storage battery pack and a diesel generator), and leads out the residual heat of a reactor core in a grading relay manner and sends the residual heat to a final heat sink. The traditional nuclear power plant waste heat discharge system strongly depends on external electric power, and under the condition that the external electric power is lost, the waste heat of a reactor core cannot be cooled and taken away, so that nuclear safety accidents, such as Fudao nuclear accidents, are caused.
The novel third-generation nuclear power station adopts a passive residual heat removal system, the passive residual heat removal system needs to overcome the flowing pressure drop in a reactor primary circuit, a secondary circuit and a cooling water circuit to form circulation, heat is transferred to a final heat sink in a one-level manner, although the residual heat removal system adopts natural circulation, external electric power is not relied on, the structure of the residual heat removal system is complex, the volume is large, the operation and maintenance are difficult, and the system is not suitable for narrow and small valuable space of an underwater unmanned underwater vehicle.
Therefore, the problem that how to provide an inherently safe, light, compact, simple and reliable reactor waste heat passive discharge system is limited by the precious cabin space resources of the underwater unmanned underwater vehicle, the complex underwater environment and the unmanned conditions is urgently needed to be solved by the technical staff in the field.
Disclosure of Invention
In view of this, the invention provides a passive residual heat removal system for an underwater nuclear power unmanned underwater vehicle, which has a simple structure and can passively achieve reactor residual heat removal for the underwater nuclear power unmanned underwater vehicle.
In order to achieve the purpose, the invention adopts the following technical scheme: a passive residual heat removal system for an underwater nuclear powered unmanned vehicle, the system comprising: a heat insulation member, a waste heat discharge chamber;
the heat insulation piece sleeve is positioned on the outer surface of each heat pipe in the heat pipe bundle of the reactor;
the waste heat discharge chamber is sleeved on the periphery of the heat pipe bundle, is in a cylindrical shape with one open end, the open end of the waste heat discharge chamber penetrates through the heat pipe bundle and is in sealing connection with the reactor, the other end face of the waste heat discharge chamber is provided with a plurality of holes, and the heat pipes in the heat pipe bundle penetrate through the punched holes;
the waste heat discharge cavity is provided with an outlet and an inlet from top to bottom respectively, a lower valve is installed at the inlet, and an upper valve is installed at the outlet.
Preferably, the external thermal insulation piece is made of thermal insulation material and directly wraps the external of the heat pipe, or is a sleeve which is sleeved on the external of the heat pipe and is provided with a certain gap, and the gap is filled with thermal insulation gas.
Preferably, the residual heat is discharged from the inside of the cavity body to be vacuumized and insulated or filled with heat preservation gas to preserve heat.
Preferably, one or more groups of valves are adopted in both the lower valve and the upper valve.
Preferably, the lower valve and the upper valve are both kept closed in the power-on state and are both naturally opened in the power-off state.
Preferably, water single-phase natural convection heat transfer or nucleate boiling natural convection heat transfer between water and tube bundles is adopted in the residual heat discharging chamber.
The invention has the beneficial effects that: the passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle can continuously remove the residual heat of the reactor core of the reactor without the need of an external power supply for supplying power, when the reactor fails and the power supply is cut off, a valve at the lower part of a residual heat removal chamber is opened to introduce an external cooling water source, the external water source flows through a reactor heat pipe bundle to take away heat, passive natural circulation is established, the density of the cooled water after temperature rise is reduced, and the cooled water is removed from a valve at the upper part of the residual heat removal chamber.
In the waste heat discharge system, the heat insulation piece is designed on the outer side of the heat pipe, so that the heat pipe can be prevented from being directly contacted with seawater, and the corrosion damage of the heat pipe caused by the direct contact of the heat pipe and the seawater is avoided; secondly, the purpose is to reduce the temperature gradient and avoid the phenomenon of film boiling heat exchange, which leads to the failure of the cooling effect.
Drawings
FIG. 1 is a schematic structural diagram of a passive residual heat removal system for an underwater nuclear power unmanned underwater vehicle, provided by the invention;
FIG. 2 is a left side view of the structure of the passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle;
in the figure: 1. the reactor 2, the heat pipe bundle 3, the heat insulation piece 4, the waste heat discharge chamber 5, the lower valve 6 and the upper valve.
Detailed Description
It will be appreciated by those of ordinary skill in the art that the embodiments described herein are intended to assist the reader in understanding the principles of the invention and are to be construed as being without limitation to such specifically recited embodiments and examples. Those skilled in the art can make various other specific changes and combinations based on the teachings of the present invention without departing from the spirit of the invention, and these changes and combinations are within the scope of the invention.
The invention is described in detail below with reference to the figures and specific embodiments.
The invention discloses a passive residual heat removal system for an underwater nuclear power unmanned underwater vehicle, which is shown in figures 1 and 2 and comprises: a heat insulating member 3 and a residual heat discharging chamber 4.
The heat insulation piece 3 is made of heat insulation material and directly wraps the heat pipe, or is a sleeve which is sleeved outside the heat pipe and is provided with a certain gap, and the gap is filled with heat insulation gas. The heat insulation piece is a heat transfer piece, but the heat transfer rate is low, and the purpose of arranging the heat insulation piece is that the heat insulation piece can prevent the heat pipe from directly contacting with seawater, so that the corrosion damage of the heat pipe caused by the direct contact of the heat pipe and the seawater is avoided; secondly, the heat insulation piece can reduce the temperature gradient, and avoid the phenomenon of film boiling heat transfer, resulting in that the cooling effect can not be achieved. In addition, when the reactor normally operates, the heat insulation piece can reduce the heat loss of the heat pipe and improve the utilization efficiency of the reactor.
The residual heat discharging chamber 4 is sleeved on the periphery of the heat pipe bundle 2, the residual heat discharging chamber 4 is in a cylindrical shape with one open end, the open end of the residual heat discharging chamber passes through the heat pipe bundle 2 and then is hermetically connected with the reactor 1, a plurality of holes are formed in the other end face of the residual heat discharging chamber, and heat pipes in the heat pipe bundle 2 pass through the punched holes.
An outlet and an inlet are respectively arranged at the upper part and the lower part of the waste heat discharge cavity 4, a lower valve 5 is arranged at the inlet, and an upper valve 6 is arranged at the outlet. The other ends of the upper valve 5 and the lower valve 6 are connected with an external water source, such as seawater or a safety water injection tank.
The waste heat discharge cavity 4 is filled with heat preservation gas before the upper valve 5 and the lower valve 6 are opened, or the heat loss of the heat pipe is placed through vacuum heat insulation. The residual heat discharging chamber 4 adopts water single-phase natural convection heat transfer or nucleate boiling natural convection heat transfer between water and tube bundles.
The lower valve 5 and the upper valve 6 both adopt one or more groups of valves, the two valves are kept closed in the power-on state and are naturally opened in the power-off state, and an external water source cooling heat pipe is introduced to take away the waste heat of the reactor core.
The working process of the passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle is as follows:
when the nuclear heat of the reactor core cannot be led out due to the system failure of the two-loop or three-loop of the heat pipe reactor, namely the heat trap loss accident, the reactor is stopped immediately, and the decay waste heat of the reactor still needs to be continuously cooled and led out. The upper valve and the lower valve of the waste heat discharge chamber lose electric power under accident conditions, the valves are automatically opened, an external water source, such as seawater or a water source in a safety injection water tank enters the waste heat discharge chamber from the lower valve, and original heat preservation gas in the waste heat discharge chamber is discharged to the outside from the valve at the upper end of the chamber. Because the temperature of the heat pipe is extremely high, in order to avoid rapid boiling after an external water source is contacted with the heat pipe, the phenomenon of film boiling heat exchange is generated, and heat exchange is worsened, an external heat insulation part is wrapped on the surface of the heat pipe in advance, and the direct contact between the heat pipe and the external water source is avoided, so that the temperature gradient is reduced. The external water source discharges the decay waste heat of the reactor core to the outside through water single-phase natural convection heat transfer or nuclear boiling natural convection heat transfer between water and the tube bundle in the waste heat discharge chamber.
Claims (6)
1. A passive residual heat removal system for an underwater nuclear powered unmanned vehicle, the system comprising: a heat insulation piece (3) and a residual heat discharge chamber (4);
the heat insulation piece (3) is positioned on the outer surface of each heat pipe in the heat pipe bundle (2) of the reactor (1);
the waste heat discharge chamber (4) is sleeved on the periphery of the heat pipe bundle (2), the waste heat discharge chamber (4) is in a cylindrical shape with one open end, the open end of the waste heat discharge chamber penetrates through the heat pipe bundle (2) and then is hermetically connected with the reactor (1), a plurality of holes are formed in the other end face of the waste heat discharge chamber, and heat pipes in the heat pipe bundle (2) penetrate through the punched holes;
the upper part and the lower part of the waste heat discharge cavity (4) are respectively provided with an outlet and an inlet, the inlet is provided with a lower valve (5), and the outlet is provided with an upper valve (6).
2. The passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle as claimed in claim 1, wherein the heat insulation member (3) is made of a heat insulation material and directly wraps the heat pipe, or is a sleeve pipe which is sleeved outside the heat pipe and is provided with a certain gap, and the gap is filled with heat insulation gas.
3. The passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle according to claim 1, wherein the interior of the residual heat removal cavity (4) is vacuumized and insulated or filled with heat preservation gas for heat preservation.
4. The passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle according to claim 1, characterized in that one or more groups of valves are adopted for the lower valve (5) and the upper valve (6).
5. The passive residual heat removal system for the underwater nuclear powered unmanned vehicle of claim 1, wherein the lower valve (5) and the upper valve (6) are kept closed in an energized state and are naturally opened in a de-energized state.
6. The passive residual heat removal system for the underwater nuclear power unmanned underwater vehicle as claimed in claim 1, wherein the residual heat removal chamber (4) adopts water single-phase natural convection heat exchange or nuclear boiling natural convection heat exchange between water and tube bundles.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110158816.7A CN112967824A (en) | 2021-02-05 | 2021-02-05 | Passive residual heat removal system for underwater nuclear power unmanned underwater vehicle |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110158816.7A CN112967824A (en) | 2021-02-05 | 2021-02-05 | Passive residual heat removal system for underwater nuclear power unmanned underwater vehicle |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN112967824A true CN112967824A (en) | 2021-06-15 |
Family
ID=76274116
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110158816.7A Pending CN112967824A (en) | 2021-02-05 | 2021-02-05 | Passive residual heat removal system for underwater nuclear power unmanned underwater vehicle |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112967824A (en) |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0418701A1 (en) * | 1989-09-19 | 1991-03-27 | Mitsubishi Jukogyo Kabushiki Kaisha | Reactor core decay heat removing system in a pressurized water reactor |
| CN107144035A (en) * | 2017-05-16 | 2017-09-08 | 中国科学院广州能源研究所 | A kind of regulatable loop heat pipe formula underground heat mining system of working medium circulation flow |
| CN110246598A (en) * | 2018-03-09 | 2019-09-17 | 韩国原子力研究院 | Dependent response heap chamber cooling system |
| CN110739090A (en) * | 2019-10-14 | 2020-01-31 | 哈尔滨工程大学 | passive waste heat removal system of heat pipe stack cooled by wall surface of pressure container |
| CN111554416A (en) * | 2020-05-29 | 2020-08-18 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Waste heat discharge system of heat pipe stack |
| CN111724917A (en) * | 2020-07-17 | 2020-09-29 | 中国工程物理研究院核物理与化学研究所 | Heat pipe stack coupling supercritical CO2Cyclic nuclear power plant and method of use |
| CN111968764A (en) * | 2020-08-22 | 2020-11-20 | 西安交通大学 | Liquid nuclear fuel heat pipe reactor power supply system and method for recompression Brayton cycle |
-
2021
- 2021-02-05 CN CN202110158816.7A patent/CN112967824A/en active Pending
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0418701A1 (en) * | 1989-09-19 | 1991-03-27 | Mitsubishi Jukogyo Kabushiki Kaisha | Reactor core decay heat removing system in a pressurized water reactor |
| CN107144035A (en) * | 2017-05-16 | 2017-09-08 | 中国科学院广州能源研究所 | A kind of regulatable loop heat pipe formula underground heat mining system of working medium circulation flow |
| CN110246598A (en) * | 2018-03-09 | 2019-09-17 | 韩国原子力研究院 | Dependent response heap chamber cooling system |
| CN110739090A (en) * | 2019-10-14 | 2020-01-31 | 哈尔滨工程大学 | passive waste heat removal system of heat pipe stack cooled by wall surface of pressure container |
| CN111554416A (en) * | 2020-05-29 | 2020-08-18 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Waste heat discharge system of heat pipe stack |
| CN111724917A (en) * | 2020-07-17 | 2020-09-29 | 中国工程物理研究院核物理与化学研究所 | Heat pipe stack coupling supercritical CO2Cyclic nuclear power plant and method of use |
| CN111968764A (en) * | 2020-08-22 | 2020-11-20 | 西安交通大学 | Liquid nuclear fuel heat pipe reactor power supply system and method for recompression Brayton cycle |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN107293338B (en) | Nuclear reactor safety system | |
| KR101071415B1 (en) | High pressure safety injection tank system for loca and sbo | |
| US9536629B2 (en) | Passive power production during a nuclear station blackout | |
| CN107403650B (en) | Secondary side passive waste heat discharging system of offshore floating nuclear power station | |
| US20240029904A1 (en) | Integrated passive reactor | |
| CN113808764B (en) | Method and system for guiding out residual heat of reactor core in containment | |
| WO2022135245A1 (en) | Passive safety system for reactor | |
| CN113178272B (en) | Passive residual heat removal system of nuclear power unmanned submersible vehicle and working method | |
| CN110739090A (en) | passive waste heat removal system of heat pipe stack cooled by wall surface of pressure container | |
| CN111446013A (en) | Marine environment secondary side passive waste heat removal system and use method | |
| CN210837199U (en) | Waste heat discharge system and nuclear power system | |
| CN110010255B (en) | Lead-cooled fast reactor waste heat discharging system and discharging method | |
| CN104078086A (en) | Active and passive combined containment sump water cooling system | |
| CN112967824A (en) | Passive residual heat removal system for underwater nuclear power unmanned underwater vehicle | |
| JP2015505373A (en) | Power generation module | |
| CN107799190A (en) | A kind of pressurized water reactor peculiar to vessel and its primary side non-kinetic residual heat removal system | |
| JP6305935B2 (en) | Diving energy generation module | |
| CN110648771A (en) | Nuclear power reactor cavity passive circulating cooling system based on Stirling engine | |
| CN112700893A (en) | Waste heat discharge system and method and nuclear power system | |
| CN204010703U (en) | A kind of containment sump water cooling system of active, non-active combination | |
| JP6305937B2 (en) | Submersible or underwater power generation module | |
| CN212113243U (en) | Passive residual heat removal system of marine environment secondary side | |
| CN110289110B (en) | Nuclear power vessel containment heat removal system | |
| CN114038591A (en) | Primary side passive residual heat removal system for nuclear reactor | |
| CN112768095A (en) | Containment shielding and cooling system for marine nuclear power platform |
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 |
Application publication date: 20210615 |
|
| RJ01 | Rejection of invention patent application after publication |