CN220272159U - System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition - Google Patents
System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition Download PDFInfo
- Publication number
- CN220272159U CN220272159U CN202321407460.7U CN202321407460U CN220272159U CN 220272159 U CN220272159 U CN 220272159U CN 202321407460 U CN202321407460 U CN 202321407460U CN 220272159 U CN220272159 U CN 220272159U
- Authority
- CN
- China
- Prior art keywords
- vehicle
- heat pipe
- inner shell
- leakage
- shell
- 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.)
- Active
Links
- 230000004888 barrier function Effects 0.000 claims abstract description 7
- 239000007788 liquid Substances 0.000 claims description 38
- 238000004062 sedimentation Methods 0.000 claims description 24
- 229910000831 Steel Inorganic materials 0.000 claims description 11
- 239000010959 steel Substances 0.000 claims description 11
- 239000000463 material Substances 0.000 claims description 8
- 230000002265 prevention Effects 0.000 claims description 8
- 238000005507 spraying Methods 0.000 claims description 8
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims description 7
- 239000004327 boric acid Substances 0.000 claims description 7
- 239000002699 waste material Substances 0.000 claims description 5
- 229910000975 Carbon steel Inorganic materials 0.000 claims description 4
- 239000010962 carbon steel Substances 0.000 claims description 4
- 239000011513 prestressed concrete Substances 0.000 claims description 4
- 239000011150 reinforced concrete Substances 0.000 claims description 4
- 238000007789 sealing Methods 0.000 claims description 4
- 239000007921 spray Substances 0.000 claims description 3
- 229910052693 Europium Inorganic materials 0.000 claims description 2
- YDFRFVFUBOYQIX-UHFFFAOYSA-H [B+3].C([O-])([O-])=O.C([O-])([O-])=O.C([O-])([O-])=O.[B+3] Chemical compound [B+3].C([O-])([O-])=O.C([O-])([O-])=O.C([O-])([O-])=O.[B+3] YDFRFVFUBOYQIX-UHFFFAOYSA-H 0.000 claims description 2
- OGPBJKLSAFTDLK-UHFFFAOYSA-N europium atom Chemical compound [Eu] OGPBJKLSAFTDLK-UHFFFAOYSA-N 0.000 claims description 2
- 230000002787 reinforcement Effects 0.000 claims description 2
- 238000009792 diffusion process Methods 0.000 abstract description 2
- 230000007613 environmental effect Effects 0.000 abstract description 2
- 230000004927 fusion Effects 0.000 abstract 1
- 238000013461 design Methods 0.000 description 9
- 239000004567 concrete Substances 0.000 description 5
- 238000010586 diagram Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 230000008859 change Effects 0.000 description 3
- 239000010410 layer Substances 0.000 description 3
- 238000012423 maintenance Methods 0.000 description 3
- 235000017166 Bambusa arundinacea Nutrition 0.000 description 2
- 235000017491 Bambusa tulda Nutrition 0.000 description 2
- 241001330002 Bambuseae Species 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 2
- 235000015334 Phyllostachys viridis Nutrition 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 2
- 230000009471 action Effects 0.000 description 2
- 239000011425 bamboo Substances 0.000 description 2
- 230000002457 bidirectional effect Effects 0.000 description 2
- 229910052799 carbon Inorganic materials 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000004873 anchoring Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 239000001569 carbon dioxide Substances 0.000 description 1
- 229910002092 carbon dioxide Inorganic materials 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000032798 delamination Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 239000004519 grease Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000004570 mortar (masonry) Substances 0.000 description 1
- 238000006386 neutralization reaction Methods 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 239000002356 single layer Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
Classifications
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to a system for preventing nuclide leakage of a vehicle-mounted heat pipe reactor under accident conditions. When the vehicle-mounted heat pipe reactor is applied to engineering practice, the problem of nuclide diffusion caused by external collision and other factors during normal operation needs to be considered. The anti-leakage system has the intelligent direction changing function, and the state of the operation vehicle can be judged and controlled by the external condition so as to avoid the active impact of the operation vehicle on the external environment as much as possible; secondly, when external collision occurs, the integrity of the internal reactor core can be ensured to the greatest extent, so that accidents are prevented; the collection of nuclides is realized through two barriers when an accident happens, so that the radionuclide can not be diffused into the environment when the accident happens, the personal safety and the environmental safety can be guaranteed, and the safety maximization can be realized. The anti-shell-expansion system can be suitable for various mobile nuclear energy systems, and can be applied to various fields such as remote areas, islands, space, army and civil fusion and the like.
Description
Technical Field
The utility model relates to the technical fields of energy sources including the nuclear energy field and mechanical equipment, in particular to a system for preventing nuclide leakage of a vehicle-mounted heat pipe reactor under an accident condition.
Background
The heat pipe reactor is used as a novel small reactor, has good controllability, better thermal transient feedback performance, high reliability and low maintenance requirement, and has wide application in universe exploration, resource development and nuclear energy device miniaturization. The heat pipe cooling reactor adopts the design concept of a solid reactor, and directly leads out heat from a reactor core through a high-temperature heat pipe, so that the system design is simplified, and the system is suitable for being used as a technical model selection of a small-sized nuclear power supply. The heat pipe type reactor takes a solid reactor as a core, and heat is directly transmitted to a reactor core by a high-temperature pipeline, so that the system has a simple structure and is suitable for small nuclear power generation.
The vehicle-mounted heat pipe small-sized stack can be widely applied in actual production, can effectively reduce fuel consumption and carbon dioxide emission, and plays a key role in carbon peak carbon neutralization. The heat pipe is heat exchange generated by heat exchange of the working fluid in the heat pipe, and has high heat conductivity, good isothermicity, good heat flow density variability, good temperature characteristic, good environmental adaptability and good thermal diode and heat exchange characteristic. The heat pipe is used for exchanging heat to the automobile small-sized stack, so that the heat conduction characteristic of the automobile small-sized stack can be effectively improved. The heat pipe reactor is a new small reactor, has good controllability, good heat-transient feedback characteristic, high reliability and low maintenance cost, and is widely applied to the fields of universe exploration, resource development, nuclear energy device miniaturization and the like. At present, the completion of the test of the overseas mini-space nuclear reactor Kilopower shows that the mini-heat pipe reactor has made substantial progress in aviation and ocean exploration.
The research on the heat pipe reactor at home and abroad mainly focuses on the contents such as physical and thermal design of the reactor core, material selection, self safety characteristics and the like. A movable anti-collision pipe system for a heat pipe reactor according to chinese patent No. 202110991519.0 can reduce impact on the heat pipe reactor. However, there is currently a lack of related devices and designs for how to prevent collisions of the mobile stacks onboard the vehicle actively to the outside and diffusion of nuclides to the environment.
Disclosure of Invention
The utility model aims to solve the problems in the background technology and provides a system for preventing nuclide leakage of a vehicle-mounted heat pipe reactor under an accident condition. The radionuclide is settled and collected while the radionuclide is prevented from leaking into the environment, and meanwhile, the active impact of the operation vehicle to the outside is avoided as much as possible, so that the probability of accident occurrence is reduced.
According to the technical scheme, the system for preventing nuclide leakage of the vehicle-mounted heat pipe reactor under the accident condition comprises an inner shell system, an outer shell system and a collecting system, wherein the collecting system comprises a liquid collecting pipeline, a liquid collecting pump and a liquid storage tank;
the inner shell system covers the collecting system; the inner shell system and the collecting system are combined to form a sealing structure which is used as a first barrier to protect the small heat pipe stacks arranged on the liquid storage tank;
the shell system covers the outer side of the inner shell system; a cavity is formed between the outer shell system and the inner shell system; the outer shell system changes the motion state of the working vehicle to prevent collision, monitors whether the inner shell system has nuclide leakage, and serves as a second barrier to collect the leaked nuclide.
Further, the inner shell system comprises an alarm device, a nuclide sedimentation device and an inner shell; the alarm device is arranged along the inner wall of the inner shell, and the nuclide sedimentation device is arranged at the right middle position of the inner wall of the inner shell and is positioned above the small heat pipe pile. The shell system comprises a spraying device, a positioning and turning device, a radionuclide concentration detector and a shell; the spraying device is arranged in the middle position of the inner wall of the shell and is positioned above the nuclide sedimentation device; the radionuclide concentration detector is arranged on the inner wall of the shell, monitors the concentration and is connected with the spraying device through an electric signal.
The material of the inner shell is reinforced concrete with a carbon steel lining, and the material of the outer shell is steel prestressed concrete. The accident pressure load is borne by a large number of bidirectional prestress steel bundles, so that the shell structure is free from brittle failure, the design pressure is also unrestricted, and the stress is safer and more reliable. The inner shell and the outer shell are made of thick steel bars which are densely arranged so as to bear the action of accident pressure and temperature. The inner shell and the outer shell adopt non-grouting non-bonding prestress reinforcement bars, so that the prestress steel bundles can be conveniently inspected and repaired and tensioned regularly and can be replaced as necessary. The impact of external flying objects can be shielded, and the active impact of the working vehicle to the external environment is blocked. Meanwhile, the whole surface of the outer wall of the shell is provided with a flexible material coating so as to relieve acting force when the operation vehicle collides against an obstacle, ensure the safety of the vehicle-mounted movable small reactor core and avoid serious accidents as far as possible; the top adopts flat dome, and the section of thick bamboo wall buttress is only three, and the bearing capacity of single steel strand increases one time, because the effect of ordinary reinforcing bar is fully played, the compressive stress of section of thick bamboo wall reduces. The top can also adopt a hemispherical top, so that a ring beam is omitted, and the stress performance of the anti-expansion shell structure is improved;
after the accident happens, the alarm device can start an alarm program to remind an operator after detecting an abnormal working state, and start a nuclide sedimentation device of the inner shell system to release sedimentation liquid so as to carry out first nuclide sedimentation collection. The settled liquid enters a liquid collecting pipeline under the double driving of a natural circulation and a liquid collecting pump, and finally is collected in a liquid collecting box.
Furthermore, the nuclide sedimentation device adopts boric acid solution, europium hafnate or boron carbonate in the sedimentation liquid sprayed after the accident occurs; the solubility of the boric acid solution is 3000 mug/g-50000 mug/g. Boric acid is a substance with a large neutron absorption cross section, and can reduce reactivity. The sedimentation liquid is collected into a liquid collecting box by a collecting system for subsequent treatment
Further, negative pressure is formed between the inner shell and the outer shell, so that the radionuclide can be retained on the outer surface of the inner shell as much as possible when the inner shell system escapes. Meanwhile, a plurality of small blowers are arranged between the inner shell and the outer shell, so that when the inner shell is leaked, the radionuclide does not leak outwards, and the probability of the radionuclide passing through the outer shell system can be reduced as much as possible.
The housing system includes a radionuclide concentration detector that can perform self-learning, detect radionuclide concentration while accumulating data experience, so that whether to deliver an electrical signal to the spray device for re-nuclide settling and neutron absorption can be independently determined next time. And at the same time, a signal can be sent to an operator to remind the operator of the state of the small heat pipe stack. Radionuclide concentration detectors exist in existing technology, but the combination of radionuclide concentration detectors and intelligence still requires further design and research.
The shell system comprises a positioning and turning device, so that the operation vehicle has a self-driving function, a corresponding model is established according to a large amount of data, the operation vehicle can have a prediction function after digital twinning, the self-state control can be performed in the face of external environment change, parking or turning and speed control can be performed, active collision of the operation vehicle and obstacles is avoided, and the influence of uncontrollable factors on the integrity of the vehicle-mounted heat pipe small pile is avoided. The automatic driving function of the vehicle has been applied in the advanced automobile industry, however, the application of the vehicle in engineering operation is still further required to be developed.
Compared with the prior art, the utility model has the following beneficial technical effects:
the system for preventing nuclide leakage can automatically control the state of the operation vehicle, the outer shell and the inner shell can block the impact of external flying objects, if nuclide leakage still exists, the inner shell system can give an alarm and carry out primary sedimentation on radionuclide through the nuclide sedimentation device, waste liquid is temporarily stored in the liquid storage tank through the liquid collecting pipeline, and the serious consequences caused by accidents are reduced when the nuclide is sedimentated by sedimentated liquid. And meanwhile, the intelligent positioning and turning control of the operation vehicle is performed, so that the active impact of the operation vehicle on external obstacles is avoided as much as possible.
The utility model is provided with multiple barriers, if radionuclide leaks from the inner shell, the radionuclide concentration detector on the outer shell system can detect the nuclide and start the spraying device on the outer shell system to carry out secondary radionuclide sedimentation, and the waste liquid is temporarily stored in the liquid storage tank through the liquid collecting pipeline and waits for subsequent treatment. The nuclear radiation leakage is prevented in time when the heat pipe reactor is impacted, so that the leakage danger caused by the impact is reduced, the safety performance of the small heat pipe reactor is effectively improved, and the environment and personal safety are ensured.
The system for preventing nuclide from diffusing has the advantages of good economy, strong safety performance and convenient inspection and maintenance, and can meet the nuclide leakage prevention requirement of the vehicle-mounted heat pipe reactor. The method can be used for various small nuclear reactors, especially mobile heat pipe reactors, which need to provide nuclear leakage prevention.
Drawings
FIG. 1 is a schematic diagram of the overall structure of a vehicle-mounted heat pipe reactor according to an embodiment of the present utility model;
FIG. 2 is a schematic diagram of the internal housing system of the in-vehicle heat pipe reactor nuclide leakage prevention system of the embodiment of FIG. 1;
FIG. 3 is a schematic diagram of the housing system of the in-vehicle heat pipe reactor nuclide leakage prevention system of the embodiment of FIG. 1;
FIG. 4 is a schematic diagram of a waste liquid collection system according to an embodiment of the present utility model.
In the figure: 1. an inner shell system; 11. an alarm device; 12. a nuclide sedimentation device; 13. an inner case;
2. a housing system; 21. a spraying device; 22. positioning a direction changing device; 23. a radionuclide concentration detector; 24. a housing;
3. a collection system; 31. a liquid collecting pipeline; 32. a liquid collecting pump; 33. a liquid storage tank;
4. a small stack of heat pipes.
Detailed Description
Example 1
The system for preventing nuclide leakage of the vehicle-mounted mobile heat pipe reactor of the embodiment comprises an inner shell system 1 and an outer shell system 2 as shown in fig. 1, wherein the inner shell system 1 comprises an alarm device 11, a nuclide sedimentation device 12 and an inner shell 13. The alarm device 11 plays a role in monitoring, and if an accident occurs, the alarm device 11 detects an alarm signal and starts the nuclide sedimentation device 12 to spray boric acid solution for carrying out first nuclide sedimentation collection; the radionuclides are collected, waste liquid is conveyed into the liquid storage tank 33 through the liquid collecting pipeline 31 and the drive of the liquid collecting pump 32 machine in the closed space of the inner shell 13 for waiting for subsequent treatment, and serious consequences caused by the leakage of the radionuclides into the environment are reduced.
In addition, the pressure at the inner shell 13 can be reduced by a vacuum pump, and a negative pressure environment is formed inside the inner shell 13; meanwhile, a plurality of small blowers are arranged between the inner shell 13 and the outer shell 24, and can blow air from the outer shell 24 to the inner shell 13, so that radionuclides do not leak outwards when the inner shell 13 leaks.
In the running process of the working vehicle, the external environment can change, the working vehicle possibly has active impact on an external object, the positioning and direction changing device 22 enables the working vehicle to have a self-driving function, a corresponding model is built according to a large amount of data, the working vehicle can have a prediction function after digital twinning, the self-state control can be performed in the face of the external environment change, parking, direction changing and speed control can be performed, the active impact of the working vehicle and an obstacle is avoided, the integrity of the vehicle-mounted heat pipe small pile 4 is guaranteed, and accidents are avoided as much as possible.
The inner shell system 1 and the outer shell system 2 employ densely arranged rebar to withstand the effects of accident pressures and temperatures. As shown in fig. 2, the material of the inner shell 13 is reinforced concrete lined with carbon steel to withstand the effects of accident pressure and temperature. The shell 2 is made of steel prestressed concrete, and accident pressure load is borne by a large number of bidirectional prestressed steel bundles, so that the anti-expansion shell structure cannot be subjected to brittle failure, design pressure can be unrestricted, and stress is safer and more reliable. The steel lining of the dome portion may be assembled by a bracket support or may be integrally hoisted after the ground assembly. The dome is usually first poured with a concrete primary layer of about 20 cm in thickness, then with the primary layer shell as support, and then with the rest of the concrete. The individual shells enlarge the dome anchoring ribs so that the dome concrete can be poured continuously in a circumferential direction in circles towards the centre without delamination. After the concrete is solidified, the prestressed steel bundles are penetrated into a preset pore canal in the shell to be stretched; after tensioning, the steel bundles and the anchorage devices thereof are sealed by anti-corrosion grease or mortar in time. The leakage at the design event pressure is generally not more than 0.1 to 0.5% of the total weight of containment free volume air within 24 hours. Thus, good sealing measures are necessary for hundreds of various penetrations in the inner and outer shells as well as the shell structure itself. For the reinforced concrete or prestressed concrete single-layer containment, lining plates with perfect integrity are required to ensure the air tightness of the containment. Most liners use thin carbon steel sheets. The lining plate should be anchored reliably to the concrete housing wall and the inner surface should be coated with an anti-corrosive layer.
If there is no leak on the inner housing, the outer housing radionuclide concentration detector 23 will detect no radionuclide, so that only the devices inside the space of the inner housing 13 need to be treated when accident post-treatment is performed. If the intelligent radionuclide concentration detector 23 on the outer shell 24 detects that the radionuclide leaks from the inner shell 13, the intelligent radionuclide concentration detector 23 reminds the monitor of entering an emergency state, and simultaneously opens the spraying device 21 to perform secondary radionuclide sedimentation, the device is shown in fig. 3, the radionuclide and the boric acid can reach the sloping plate at the bottom along the gap between the inner shell and the outer shell after being mixed, and reach the liquid collecting pipeline 31 through the action of gravity, and enter the liquid storage tank 33 through the driving of the liquid collecting pump 32, as shown in fig. 4. The inner shell 13 and outer shell 24 form two traps for radionuclide leakage, achieving multiple barriers. Depending on safety requirements, care must be taken in the design of the inner shell 13 and the outer shell 24 with regard to the integrity and reliability of the shell structure. In addition to the use of strict and reliable calculation means, strict quality control is required for the material, manufacture, inspection and the like of the inner shell and the outer shell.
The embodiments of the present utility model have been described in detail with reference to the drawings, but the present utility model is not limited thereto, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present utility model.
Claims (10)
1. A system for preventing nuclide leakage of a vehicle-mounted heat pipe reactor under accident conditions, which comprises an inner shell system (1), an outer shell system (2) and a collecting system (3), and is characterized in that the collecting system (3) comprises a liquid collecting pipeline (31), a liquid collecting pump (32) and a liquid storage tank (33);
the inner shell system (1) covers the collecting system (3); the inner shell system (1) and the collecting system (3) are combined to form a sealing structure, and the sealing structure is used as a first barrier to protect the small heat pipe stacks (4) arranged on the liquid storage tank (33);
the shell system (2) covers the outer side of the inner shell system (1); a cavity is formed between the outer shell system (2) and the inner shell system (1); the outer shell system (2) changes the motion state of the working vehicle to prevent collision, and monitors whether the inner shell system (1) has nuclide leakage or not, and the nuclide leakage is collected as a second barrier.
2. A vehicle-mounted heat pipe reactor nuclear leakage prevention system according to claim 1, characterized in that the inner shell system (1) comprises an alarm device (11), a nuclear sedimentation device (12) and an inner shell (13); the alarm device (11) is arranged along the inner wall of the inner shell (13), and the nuclide sedimentation device (12) is arranged at the right middle position of the inner wall of the inner shell (13) and is positioned above the small heat pipe pile (4).
3. A vehicle-mounted heat pipe reactor nuclear leakage prevention system according to claim 1, characterized in that the housing system (2) comprises a spray device (21), a positioning deviator (22), a radionuclide concentration detector (23) and a housing (24); the spraying device (21) is arranged at the middle position of the inner wall of the shell (24) and is positioned above the nuclide sedimentation device (12); the radionuclide concentration detector (23) is arranged on the inner wall of the shell (24), and the radionuclide concentration detector (23) monitors the concentration and is electrically connected with the spraying device (21).
4. A system for preventing nuclear leakage of a vehicle-mounted heat pipe reactor in an accident situation according to claim 1, characterized in that the material of the inner shell (13) is reinforced concrete with carbon steel lining and the material of the outer shell (24) is steel prestressed concrete.
5. A system for preventing nuclear leakage in a vehicular heat pipe reactor in an accident situation according to claim 4, wherein the inner shell (13) and the outer shell (24) are prestressed reinforcement without grouting and bonding.
6. A vehicle-mounted heat pipe reactor nuclear leakage prevention system according to claim 1, wherein the alarm device (11) detects the alarm signal and opens the nuclear sedimentation device (12) for the first nuclear sedimentation collection.
7. The system for preventing nuclear species leakage in a vehicle-mounted heat pipe reactor under accident conditions according to claim 1, wherein boric acid solution, europium hafnate or boron carbonate is adopted in the sedimentation liquid sprayed by the nuclear species sedimentation device (12); the solubility of the boric acid solution is 3000 mug/g-50000 mug/g.
8. A system for preventing nuclear species leakage in an on-board heat pipe reactor in an accident situation according to claim 1, wherein the nuclear species settling device (12) stores the waste liquid containing the radionuclides in the liquid storage tank (33) by means of the natural circulation and liquid collecting pump (32).
9. A vehicle-mounted heat pipe reactor nuclear leakage prevention system according to claim 1, wherein the pressure at the inner shell (13) is reduced by a vacuum pump, and a negative pressure environment is formed inside the inner shell (13); meanwhile, a plurality of small blowers are arranged between the inner shell (13) and the outer shell (24), and can blow air from the outer shell (24) to the inner shell (13), so that when the inner shell (13) is leaked, the radionuclide does not leak outwards.
10. A system for preventing nuclear species leakage in a vehicle-mounted heat pipe reactor in an accident situation according to claim 1, wherein the deviator (22) is positioned such that the vehicle is self-driving, avoiding active impact of the vehicle with obstacles.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202321407460.7U CN220272159U (en) | 2023-06-05 | 2023-06-05 | System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202321407460.7U CN220272159U (en) | 2023-06-05 | 2023-06-05 | System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition |
Publications (1)
Publication Number | Publication Date |
---|---|
CN220272159U true CN220272159U (en) | 2023-12-29 |
Family
ID=89314818
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202321407460.7U Active CN220272159U (en) | 2023-06-05 | 2023-06-05 | System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN220272159U (en) |
-
2023
- 2023-06-05 CN CN202321407460.7U patent/CN220272159U/en active Active
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Zheng et al. | The general design and technology innovations of CAP1400 | |
CN112863704B (en) | Device for retaining core melt in severe accident of nuclear power plant | |
CN201741419U (en) | Main water supply flow control system of nuclear power plant | |
CN202887747U (en) | Combined active and passive reactor cavity water injecting and cooling system | |
CN205810388U (en) | A kind of deep-wall type normal pressure supplying heat nuclear reactor | |
CN220272159U (en) | System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition | |
Belyaev et al. | The world’s first floating NPP: Origination and direction of future development | |
CN117095839A (en) | System for preventing nuclide leakage of vehicle-mounted heat pipe reactor under accident condition | |
Kwant et al. | PRISM—liquid metal cooled reactor plant design and performance | |
US4687625A (en) | Piping of nuclear reactor containment vessel | |
CN217008664U (en) | Nuclear energy heat supply reactor arrangement structure of shared reactor factory building | |
CN115478721B (en) | Nuclear island factory building structure is arranged to nuclear power plant list heap | |
CN107863167A (en) | A kind of more heap arrangements of the small-sized heap of modular | |
CN113808768B (en) | Nuclear energy heat supply reactor arrangement method for double-reactor shared reactor plant | |
US10079076B2 (en) | Emergency core cooling system for a water-cooled reactor system | |
Takahashi et al. | Construction of the Monju prototype fast breeder reactor | |
Altes | Containment concepts for high temperature reactors | |
Wessman et al. | HTGR plant safety design bases | |
Marguet | The Nuclear Island | |
CN113113162A (en) | Containment cooling system of small reactor | |
CN117790014A (en) | Built-in water tank structure of spherical containment | |
Braun et al. | Nuclear reactor apparatus | |
Gronemeyer et al. | 75,000 Kilowatts of Electricity by Nuclear Fission at the Hallam Nuclear Power Facility | |
None | Supplement to SRE Safety Analysis Report | |
Shaver et al. | Review of Reactor Safety Analyses of Fast and Liquid Metal Cooled Reactors |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant |