CN110600156B - Circulation cooling method for spent fuel transfer container of million-kilowatt nuclear power plant - Google Patents
Circulation cooling method for spent fuel transfer container of million-kilowatt nuclear power plant Download PDFInfo
- Publication number
- CN110600156B CN110600156B CN201910811917.2A CN201910811917A CN110600156B CN 110600156 B CN110600156 B CN 110600156B CN 201910811917 A CN201910811917 A CN 201910811917A CN 110600156 B CN110600156 B CN 110600156B
- Authority
- CN
- China
- Prior art keywords
- spent fuel
- transfer container
- fuel transfer
- container
- cooling
- 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
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
- G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of spent fuel treatment of million kilowatt nuclear power stations, and particularly relates to a circulating cooling method of a spent fuel transfer container of a million kilowatt nuclear power station, which comprises the steps of filling compressed gas into an inner cavity of the spent fuel transfer container until radioactivity in the inner cavity reaches a preset radioactivity value; and then the spent fuel transfer container is filled with demineralized water, the demineralized water can effectively avoid boric acid crystallization caused by overhigh temperature in the inner cavity of the spent fuel transfer container, then the spent fuel transfer container is filled with boron water through the boron water, and the boron water is continuously filled for circulating cooling, so that the inner cavity stably reaches the preset temperature, and a series of operations such as subsequent unloading, outer cover removal and the like are facilitated.
Description
Technical Field
The invention belongs to the technical field of spent fuel treatment of million-kilowatt nuclear power stations, and particularly relates to a circulating cooling method for a spent fuel transfer container of a million-kilowatt nuclear power station.
Background
Spent fuel is a nuclear fuel that has been irradiated with radiation and used, and is produced by a nuclear reactor in a nuclear power plant. Nuclear fuel after nuclear reactor reactions contains a large amount of radioactive elements and therefore has a large amount of radioactivity, which, if not properly disposed of, can seriously affect the environment and the health of the personnel in contact with them. Along with the service time of the nuclear power unit is prolonged, the spent fuel assemblies generated by operation are accumulated year by year and approach to reach the design capacity of a spent fuel pool, and the spent fuel is transported out of the spent fuel pool by considering the use of a transport container. After the spent fuel transportation container is filled, helium is required to be filled into the container to establish thermal balance between a spent fuel assembly cladding and a cavity, the maximum temperature of a spent fuel assembly in the transportation container reaches 273 ℃, the average temperature of helium in the cavity is about 200 ℃ and the temperature of a container shell exceeds 85 ℃ after the spent fuel is fully loaded to reach a thermal balance state. Before the unloading operation, the inner cavity of the container needs to be filled with water and exhausted, and cooling circulation is carried out simultaneously, so that the temperature of the outer surface of the spent fuel transport container is lower than 35 ℃, and a series of operations such as unloading and outer cover removal are facilitated.
Disclosure of Invention
The invention aims to provide a circulating cooling method for a spent fuel transfer container of a million-kilowatt nuclear power plant, and aims to solve the technical problem that spent fuel in the prior art needs to be cooled so as to facilitate discharging and outer cover removal.
In order to achieve the purpose, the invention adopts the technical scheme that: a circulation cooling method for a spent fuel transfer container of a million kilowatt nuclear power plant is used for cooling the spent fuel transfer container and comprises the following steps:
setting a preset radiation value and a preset temperature for the inner cavity of the spent fuel transfer container;
filling compressed gas into the inner cavity until the radiation value of the inner cavity reaches the preset radiation value;
filling the inner cavity with demineralized water, and then filling the inner cavity with boric water;
continuously cooling the boron-filled water in the inner cavity in a circulating manner to reduce the temperature of the inner cavity to the preset temperature;
and discharging all the boron water in the inner cavity.
Further, in the step of filling the inner cavity with compressed gas, a compressed air device communicated with the spent fuel transfer container is provided, the compressed air device continuously blows air to the spent fuel transfer container for more than 30min, and the air pressure is 0.2 MPa.
Further, a discharge cooling device is provided which is respectively communicated with the spent fuel transfer container and the compressed air device, and the discharge cooling device can transmit wind of the compressed air device to the spent fuel transfer container.
Further, a shielding and filtering device which is communicated with the spent fuel transferring container and is used for filtering the gas discharged from the spent fuel transferring container is provided, and the tail end of the shielding and filtering device is provided with a detection structure for detecting the radioactivity of the discharged gas.
Further, the pair of the said armsThe fuel transfer container is filled with demineralized water, and specifically comprises the following steps: injecting 1m into the spent fuel transfer container3And the flow rate of the desalted water is 2m3/h。
Further, the filling of the boric water into the transfer container specifically comprises: continuously injecting boron water into the spent fuel transfer container, wherein the flow rate is 5.6m3/h。
Further, a canning pool is provided, the inside of the canning pool is provided with the boron water, the spent fuel is transported the container and is discharged the boron water is arranged extremely in the canning pool.
Further, the circulating cooling of the spent fuel transfer container specifically comprises: and providing a high-flow submersible pump, circularly stirring the canning pool through the high-flow submersible pump, and continuously injecting the boron water at the bottom of the canning pool into the spent fuel transfer container.
Further, the continuously injecting the boron water at the bottom of the canning pool into the spent fuel transfer container specifically comprises: detect the temperature of the delivery port department of container is transported to spent fuel, if the temperature of delivery port is greater than 35 ℃ to pause the cooling when being less than 40 ℃ the container is transported to spent fuel, and opens through the torque wrench the inner cup bolt of container is transported to spent fuel, if can open, stops the cooling.
Further, the continuously injecting the boron water at the bottom of the canning pool into the spent fuel transfer container specifically comprises: detect the temperature of the delivery port department of container is transported to spent fuel, if the temperature of delivery port is greater than 40 ℃, or is greater than 35 ℃ and be less than 40 ℃ but can't open during the inner cup bolt, to 2m are poured into in the container is transported to spent fuel3And (4) cooling by continuously supplementing the boric water, and stopping cooling when the water temperature at the water outlet is 35 ℃.
The invention has the beneficial effects that: the invention relates to a circulating cooling method of a spent fuel transfer container of a million kilowatt nuclear power plant, which comprises the steps of filling compressed gas into an inner cavity of the spent fuel transfer container until the radioactivity in the inner cavity reaches a preset radioactivity value; and then the spent fuel transfer container is filled with demineralized water, the demineralized water can effectively avoid boric acid crystallization caused by overhigh temperature in the inner cavity of the spent fuel transfer container, then the spent fuel transfer container is filled with boron water through the boron water, and the boron water is continuously filled for circulating cooling, so that the inner cavity stably reaches the preset temperature, and a series of operations such as subsequent unloading, outer cover removal and the like are facilitated.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
Fig. 1 is a schematic flow chart of a method for circularly cooling a spent fuel transfer container of a million kilowatt nuclear power plant according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a circulation cooling method for a spent fuel transfer container of a million kilowatt nuclear power plant according to an embodiment of the present invention.
Wherein, in the figures, the respective reference numerals:
10-spent fuel transfer vessel; 20-a discharge cooling device;
30-a shielded filter device; and 40, an ice storage pool.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to fig. 1-2 are exemplary and intended to be illustrative of the invention and should not be construed as limiting the invention.
In the description of the present invention, it is to be understood that the terms "length", "width", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", and the like, indicate orientations or positional relationships based on the orientations or positional relationships illustrated in the drawings, and are used merely for convenience in describing the present invention and for simplicity in description, and do not indicate or imply that the devices or elements referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and thus, are not to be construed as limiting the present invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically defined otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; either directly or indirectly through intervening media, either internally or in any other relationship. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
As shown in fig. 1 to 2, an embodiment of the present invention provides a circulation cooling method for a spent fuel transfer container of a million kilowatt nuclear power plant, which is used for cooling a spent fuel transfer container 10, and includes the following steps:
s1: setting a preset radiation value and a preset temperature for the inner cavity of the spent fuel transfer container 10;
s2: filling a compressed gas into the inner cavity of the spent fuel transfer container 10 until the radioactivity in the spent fuel transfer container 10 reaches a preset radioactivity value; specifically, the radioactivity is detected as the radioactivity of the air passing through the interior of the spent fuel transport container 10 and compared with a predetermined radioactivity.
S3: filling demineralized water into the spent fuel transfer container 10, and filling boron water into the spent fuel transfer container 10; the desalted water is filled into the spent fuel transfer container 10 and is injected into the spent fuel transfer container 1m3And the flow rate of the desalted water is 2m3H is used as the reference value. Specifically, a container containing demineralized water is provided, and a submersible pump is placed in the container containing demineralized water when 1m of the demineralized water is injected3The submersible pump is put into a tank filling pool filled with boron water, and the flow rate of the boron water is 5.6m3/h。
S4: and continuously filling boron water into the spent fuel transfer container 10 for circulating cooling, so that the temperature of the inner cavity is reduced to a preset temperature. Continuously using the submersible pump to fill boron water into the spent fuel transfer container 10, using the high-flow submersible pump to stir the filling tank filled with the boron water, and detecting the radioactive value of the boron water in the filling tank after running for 8 hours.
S5: if the emission value detected in step S4 satisfies the requirement, the boron water in the spent fuel transfer container 10 is discharged.
According to the circulating cooling method of the spent fuel transfer container of the million kilowatt nuclear power plant, disclosed by the embodiment of the invention, compressed gas is filled in the inner cavity of the spent fuel transfer container 10 until the radioactivity in the inner cavity reaches the preset radioactivity value; and then the spent fuel transfer container 10 is filled with demineralized water, the demineralized water can effectively avoid the crystallization of boric acid caused by overhigh temperature in the inner cavity of the spent fuel transfer container 10, the spent fuel transfer container 10 is filled with boric water through the boric water, and the boric water is continuously filled for circulating cooling, so that the inner cavity stably reaches the preset temperature, and a series of operations such as subsequent unloading and outer cover removal are facilitated.
Further, in this embodiment, as shown in fig. 1, the filling of the spent fuel transport container 10 with compressed gas specifically includes: and providing a compressed air device communicated with the spent fuel transferring container 10, wherein the compressed air device continuously blows air to the spent fuel transferring container 10 for more than 30min, and the air pressure is 0.2 MPa. Specifically, the part of the air exhausted from the inner cavity is exhausted to a pipeline of the nuclear fuel ventilation system for reprocessing after being filtered and cooled.
Further, in the present embodiment, as shown in fig. 1, a discharge cooling device 20 is provided, which is respectively communicated with the spent fuel transfer container 10 and the compressed air device, and the discharge cooling device 20 can transfer the wind of the compressed air device to the spent fuel transfer container 10. By providing the discharge cooling device 20, the temperature of the air flowing through the discharge cooling device 20 can be effectively lowered.
Further, in the present embodiment, as shown in fig. 1, a shielding filter device 30 is provided, which is communicated with the spent fuel transfer container 10 and is used for filtering the gas discharged from the spent fuel transfer container 10, and a tail end of the shielding filter device 30 is provided with a detection structure for detecting the radioactivity of the discharged gas. By providing the barrier filter device 30 and providing the barrier filter device 30 with a high efficiency filter and a pressure reducing filter valve, air can be purified and discharged under reduced pressure.
Further, in this embodiment, as shown in fig. 1, the continuous injection of the boron water at the bottom of the canning pool into the spent fuel transportation container 10 specifically includes: detecting the water temperature at the water outlet of the spent fuel transferring container 10, pausing to cool the spent fuel transferring container 10 if the temperature of the water outlet is more than 35 ℃ and less than 40 ℃, opening an inner cover bolt of the spent fuel transferring container 10 through a torque wrench, and stopping cooling if the inner cover bolt can be opened.
Further, in this embodiment, as shown in fig. 1, the continuous injection of the boron water at the bottom of the canning pool into the spent fuel transportation container 10 specifically includes: detecting the water temperature at the water outlet of the spent fuel transfer container 10, and injecting 2m into the spent fuel transfer container 10 if the water outlet temperature is higher than 40 ℃, or higher than 35 ℃ and lower than 40 ℃ but the inner cover bolt cannot be opened3And (4) cooling by continuously supplementing boron water, and stopping cooling when the water temperature at the water outlet is 35 ℃. Specifically, an ice storage tank 40 is provided, and the ice storage tank 40 is communicated with the discharge cooling device 20, ice cubes are conveyed from the ice storage tank 40 to the discharge cooling device 20, and then the discharge cooling device 20 transfers the ice cubes to the inner cavity of the spent fuel transfer container 10, and the spent fuel transfer container 10 is cooled by the ice cubes.
The present invention is not limited to the above preferred embodiments, and any modifications, equivalent substitutions and improvements made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (10)
1. A circulation cooling method of a spent fuel transfer container of a million kilowatt nuclear power plant is used for cooling the spent fuel transfer container, and is characterized in that: the method comprises the following steps:
setting a preset radiation value and a preset temperature for the inner cavity of the spent fuel transfer container;
filling compressed gas into the inner cavity until the radiation value of the inner cavity reaches the preset radiation value;
filling the inner cavity with demineralized water, and then filling the inner cavity with boric water;
continuously cooling the boron-filled water in the inner cavity in a circulating manner to reduce the temperature of the inner cavity to the preset temperature;
and discharging all the boron water in the inner cavity.
2. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 1, characterized in that: in the step of filling the inner cavity with compressed gas, providing a compressed air device communicated with the spent fuel transfer container, wherein the compressed air device continuously blows air to the spent fuel transfer container for more than 30min, and the air pressure is 0.2 MPa.
3. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 2, is characterized in that: and providing a discharging cooling device communicated with the spent fuel transferring container and the compressed air device respectively, wherein the discharging cooling device can transmit wind of the compressed air device to the spent fuel transferring container.
4. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 3, characterized in that: and providing a shielding and filtering device communicated with the spent fuel transfer container and used for filtering the gas discharged from the spent fuel transfer container, wherein the tail end of the shielding and filtering device is provided with a detection structure for detecting the radioactivity of the discharged gas.
5. The million kilowatt nuclear power plant spent fuel according to claim 4A method for circulating cooling of a transfer container, comprising: the filling of the inner cavity with demineralized water specifically comprises: injecting 1m into the spent fuel transfer container3And the flow rate of the desalted water is 2m3/h。
6. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 5, characterized in that: the step of filling the boron water into the inner cavity comprises the following specific steps: continuously injecting boron water into the spent fuel transfer container, wherein the flow rate is 5.6m3/h。
7. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 6, characterized in that: the provided canning pool is provided, the canning pool is internally provided with the boron water, spent fuel is transported the container discharge the boron water is arranged to the canning pool.
8. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 7, characterized in that: the internal cavity circulating cooling specifically comprises the following steps: and providing a high-flow submersible pump, circularly stirring the canning pool through the high-flow submersible pump, and continuously injecting the boron water at the bottom of the canning pool into the spent fuel transfer container.
9. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 8, characterized in that: the continuous injection of the boron water at the bottom of the canning pool into the spent fuel transfer container is specifically as follows: detect the temperature of the delivery port department of container is transported to spent fuel, if the temperature of delivery port is greater than 35 ℃ to pause the cooling when being less than 40 ℃ the container is transported to spent fuel, and opens through the torque wrench the inner cup bolt of container is transported to spent fuel, if can open, stops the cooling.
10. The method for circularly cooling the spent fuel transfer container in the million kilowatt nuclear power plant according to claim 9, characterized in that: what is needed isThe continuous injection of the boron water at the bottom of the canning pool into the spent fuel transfer container is specifically as follows: detect the temperature of the delivery port department of container is transported to spent fuel, if the temperature of delivery port is greater than 40 ℃, or is greater than 35 ℃ and be less than 40 ℃ but can't open during the inner cup bolt, to 2m are poured into in the container is transported to spent fuel3And (4) cooling by continuously supplementing boron water, and stopping cooling when the water temperature at the water outlet is 35 ℃.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910811917.2A CN110600156B (en) | 2019-08-30 | 2019-08-30 | Circulation cooling method for spent fuel transfer container of million-kilowatt nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910811917.2A CN110600156B (en) | 2019-08-30 | 2019-08-30 | Circulation cooling method for spent fuel transfer container of million-kilowatt nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110600156A CN110600156A (en) | 2019-12-20 |
| CN110600156B true CN110600156B (en) | 2021-03-02 |
Family
ID=68856777
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910811917.2A Active CN110600156B (en) | 2019-08-30 | 2019-08-30 | Circulation cooling method for spent fuel transfer container of million-kilowatt nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110600156B (en) |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101504625B1 (en) * | 2014-01-02 | 2015-03-20 | 한국수력원자력 주식회사 | Coolling system for spent fuel pool |
| CN105931688A (en) * | 2016-04-21 | 2016-09-07 | 中广核核电运营有限公司 | Method for infield transporting and unloading of spent fuel in nuclear power plant |
| CN106504804A (en) * | 2016-12-30 | 2017-03-15 | 核动力运行研究所 | A kind of cooling system and method for spent fuel transport container in discharge process |
| CN107180661A (en) * | 2017-03-30 | 2017-09-19 | 中国核动力研究设计院 | A kind of spent fuel transport container residual heat removal facility |
| US9793022B1 (en) * | 2016-10-10 | 2017-10-17 | Institute Of Nuclear Energy Research | Method of decontamination for a high activity nuclear waste polluted storage canister |
| CN108899097A (en) * | 2018-07-17 | 2018-11-27 | 西安交通大学 | A kind of spentnuclear fuel storage-transport vessel inflatable drainage device |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002243888A (en) * | 2001-02-14 | 2002-08-28 | Mitsubishi Heavy Ind Ltd | Sealing method for radioactive material and cooling device |
| EP2227665B8 (en) * | 2007-12-21 | 2018-06-06 | Holtec International, Inc. | Method for preparing a container loaded with wet radioactive elements for dry storage |
| JP5063532B2 (en) * | 2008-08-25 | 2012-10-31 | 三菱電機株式会社 | Tritium sampler |
| CN104898150B (en) * | 2015-05-04 | 2017-10-10 | 中广核核电运营有限公司 | Radic and detection method |
| CN105280250A (en) * | 2015-09-15 | 2016-01-27 | 西安交通大学 | Non-active cooling system and method used for steam generator and spent fuel pool |
-
2019
- 2019-08-30 CN CN201910811917.2A patent/CN110600156B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101504625B1 (en) * | 2014-01-02 | 2015-03-20 | 한국수력원자력 주식회사 | Coolling system for spent fuel pool |
| CN105931688A (en) * | 2016-04-21 | 2016-09-07 | 中广核核电运营有限公司 | Method for infield transporting and unloading of spent fuel in nuclear power plant |
| US9793022B1 (en) * | 2016-10-10 | 2017-10-17 | Institute Of Nuclear Energy Research | Method of decontamination for a high activity nuclear waste polluted storage canister |
| CN106504804A (en) * | 2016-12-30 | 2017-03-15 | 核动力运行研究所 | A kind of cooling system and method for spent fuel transport container in discharge process |
| CN107180661A (en) * | 2017-03-30 | 2017-09-19 | 中国核动力研究设计院 | A kind of spent fuel transport container residual heat removal facility |
| CN108899097A (en) * | 2018-07-17 | 2018-11-27 | 西安交通大学 | A kind of spentnuclear fuel storage-transport vessel inflatable drainage device |
Also Published As
| Publication number | Publication date |
|---|---|
| CN110600156A (en) | 2019-12-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP2965323B1 (en) | Managing nuclear reactor spent fuel rods | |
| CN112313756B (en) | Multi-component cask for storing and transporting spent nuclear fuel | |
| CN1024229C (en) | Reactor core decay heat removing system in pressurized water reactor | |
| CN107180661B (en) | A kind of spent fuel transport container residual heat removal facility | |
| CN1918664A (en) | Passive cooling and arresting device for the molten core material | |
| CN106205749B (en) | Nuclear reactor system | |
| CN113130106B (en) | New fuel processing system and method for high-temperature gas cooled reactor | |
| CN109065192B (en) | Reactor plant layout method | |
| JPH0318792A (en) | Passive type cooling device | |
| CN202770265U (en) | Natural circulation heat exchanger for supercritical water reactor waste heat removing | |
| CN114883019A (en) | High-temperature gas cooled reactor fuel loading and unloading system and method | |
| CN110600156B (en) | Circulation cooling method for spent fuel transfer container of million-kilowatt nuclear power plant | |
| EP3723101A2 (en) | Method for the long-term storage of spent nuclear fuel and cooling and storage tank for the implementation thereof | |
| CN106338575B (en) | Liquid metal purifies experimental apparatus | |
| CN206040222U (en) | Spentnuclear fuel storage -transport vessel | |
| CN218039418U (en) | Brine discharge device for waste lithium iron phosphate battery | |
| CA2483182C (en) | Intermediate storage system for fuel elements from a nuclear facility and a method for operating such an intermediate storage system | |
| CN210692108U (en) | Circulating cooling system of spent fuel transfer container of million-kilowatt nuclear power plant | |
| CN204010703U (en) | A kind of containment sump water cooling system of active, non-active combination | |
| CN111128420A (en) | Fuel cooling system and method for offshore floating nuclear power station | |
| CN206075831U (en) | Nuclear reactor system | |
| JP2011196700A (en) | System and method for removing residual heat | |
| CN203950562U (en) | A kind of vaporising device of processing radioactive liquid waste | |
| CN111933315A (en) | Passive residual heat removal system and method for pool type lead-based reactor | |
| CN216886357U (en) | Cooling device for ship |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |