CN111744334A - Radioactive waste gas discharge system suitable for ocean nuclear power platform - Google Patents
Radioactive waste gas discharge system suitable for ocean nuclear power platform Download PDFInfo
- Publication number
- CN111744334A CN111744334A CN202010755174.4A CN202010755174A CN111744334A CN 111744334 A CN111744334 A CN 111744334A CN 202010755174 A CN202010755174 A CN 202010755174A CN 111744334 A CN111744334 A CN 111744334A
- Authority
- CN
- China
- Prior art keywords
- waste gas
- cleaning box
- cleaning
- nuclear power
- outlet
- 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
Images
Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/14—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by absorption
- B01D53/18—Absorbing units; Liquid distributors therefor
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/14—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by absorption
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/02—Treating gases
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D2257/00—Components to be removed
- B01D2257/20—Halogens or halogen compounds
- B01D2257/202—Single element halogens
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Analytical Chemistry (AREA)
- General Chemical & Material Sciences (AREA)
- Oil, Petroleum & Natural Gas (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a radioactive waste gas discharge system suitable for an ocean nuclear power platform, which relates to the field of radioactive waste gas atmospheric discharge of the ocean nuclear power platform and comprises a waste gas cleaning and collecting component and a waste gas discharge component, wherein the waste gas cleaning and collecting component comprises a cleaning box and cleaning solution loaded in the cleaning box and used for cleaning low-level waste gas, and the outer wall of the cleaning box is provided with an inlet and an outlet for replacing the cleaning solution in the cleaning box; the waste gas discharging assembly comprises a waste gas inlet pipeline which is arranged on the side wall of the cleaning box and used for guiding low-level waste gas into the cleaning box, and a waste gas discharging outlet pipeline which is arranged at the top end of the cleaning box and used for discharging the cleaned low-level waste gas. The invention can greatly reduce the activity of nuclide entering the external environment and reduce the risk of damage to marine ecology.
Description
Technical Field
The invention relates to the field of atmospheric emission of radioactive waste gas of an ocean nuclear power platform, in particular to a radioactive waste gas emission system suitable for the ocean nuclear power platform.
Background
The ocean nuclear power platform is a marine floating nuclear power station, one platform carries 1-2 reactors with certain nuclear power according to actual requirements to provide certain product services according to user requirements, such as power supply for a drilling platform, fresh water supply, island and reef supply, comprehensive guarantee for ocean fleet, power supply for deep sea exploration and exploitation, and the like, and the ocean nuclear power platform can greatly meet the requirements in the fields of scientific research, exploration and the like.
For nuclear power plants, the radioactive isotopes xenon, krypton and iodine are produced by fission during operation. Part of the nuclides is released into the reactor coolant because of the breakage of a small amount of fuel cladding. The leakage of reactor coolant in turn causes the radioactive inert gas to be released into the atmosphere within the containment. Airborne radioactive release is controlled by severely limiting reactor coolant leaks, as well as limiting the radioactive concentrations of inert gases and iodine within the reactor coolant system. The radioactive waste gas on the platform mainly comes from waste gas of a primary pressure relief box and a waste water box, the negative pressure system exhausts, the containment and the reactor cabin exhaust and the transfer tank exhaust. The waste gas radioactivity level of the primary circuit pressure relief box and the waste water box is high, the environmental influence is large, the process waste gas belongs to process waste gas, the radioactivity level of the negative pressure system exhaust, the containment and reactor cabin exhaust and the transport tank exhaust is low, and the process waste gas belongs to cabin waste gas. The radioactive waste gas is divided into high-level, medium-level and low-level waste gas, and the high-level and medium-level waste gas needs to be processed into low-level waste gas and is directly released into the atmosphere after meeting the requirements of marine environment emission. For low emission exhaust gas constituents emitted into the atmosphere there are: aerosol, iodine and inert gas. However, low level waste gas discharged into the atmosphere still has a certain nuclide activity, thus polluting the marine ecology.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a radioactive waste gas discharge system suitable for an ocean nuclear power platform, which can greatly reduce the activity of nuclides entering the external environment and reduce the risk of damage to the ocean ecology.
In order to achieve the above purposes, the technical scheme adopted by the invention is as follows:
the waste gas cleaning and collecting assembly comprises a cleaning box and cleaning solution loaded in the cleaning box and used for cleaning low-level waste gas, and an inlet and an outlet for replacing the cleaning solution in the cleaning box are formed in the outer wall of the cleaning box;
the waste gas discharging assembly comprises a waste gas inlet pipeline arranged on the side wall of the cleaning box and used for guiding low-emission waste gas to the cleaning box, and a waste gas discharging outlet pipeline arranged at the top end of the cleaning box and used for discharging the cleaned low-emission waste gas.
On the basis of the technical scheme, the inlet and the outlet comprise a waste gas cleaning box inlet used for leading in the cleaning solution to the cleaning box and a waste gas cleaning box outlet used for leading out the cleaning solution cleaned in the cleaning box.
On the basis of the technical scheme, the inlet of the waste gas cleaning box is positioned at the upper part of one side surface of the cleaning box, and the inlet of the waste gas cleaning box is provided with a waste gas cleaning box inlet pipeline.
On the basis of the technical scheme, an inlet electric valve is arranged on an inlet pipeline of the waste gas cleaning box.
On the basis of the technical scheme, the outlet of the waste gas cleaning box is positioned at the bottom of the cleaning box, and an outlet pipeline of the waste gas cleaning box is installed on the outlet of the waste gas cleaning box.
On the basis of the technical scheme, the rear part of the outlet pipeline of the waste gas cleaning box is connected with the collecting box, one end of the outlet pipeline of the waste gas cleaning box is connected with the outlet of the waste gas cleaning box, and the other end of the outlet pipeline of the waste gas cleaning box is connected with the collecting box.
On the basis of the technical scheme, an outlet electric valve is arranged on an outlet pipeline of the waste gas cleaning box.
On the basis of the technical scheme, the waste gas inlet pipeline is positioned below one side wall of the cleaning box.
On the basis of the technical scheme, one part of the waste gas inlet pipeline extends into the cleaning box, the other part of the waste gas inlet pipeline is positioned outside the cleaning box, the part of the waste gas inlet pipeline extending into the cleaning box is provided with a plurality of upward exhaust outlets, the exhaust outlets are arranged at intervals, and the part of the waste gas inlet pipeline positioned outside the cleaning box is provided with a waste gas inlet electric valve.
On the basis of the technical scheme, the cleaning solution is water.
Compared with the prior art, the invention has the advantages that: the cleaning solution is arranged in the cleaning box, low-level waste gas to be cleaned is guided to the cleaning box through the waste gas inlet pipeline, aerosol and iodine in the low-level waste gas are cleaned, the cleaned low-level waste gas enters the external atmosphere through the waste gas exhaust outlet pipeline, namely the low-level waste gas is cleaned and then is exhausted to the external environment, the aerosol and iodine nuclide in the cleaned low-level waste gas are negligible, and the nuclide entering the external atmosphere only contains inert gas, so that the nuclide activity entering the external environment is greatly reduced, and the risk of marine ecology damage is reduced.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings needed to be used in the description of the embodiments are briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present application, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without creative efforts.
Fig. 1 is a schematic structural diagram of a radioactive exhaust emission system suitable for an ocean nuclear power platform according to an embodiment of the present invention.
In the figure: 1-cleaning tank, 2-waste gas inlet pipeline, 3-waste gas discharge outlet pipeline, 4-waste gas cleaning tank inlet, 5-waste gas cleaning tank outlet, 6-waste gas cleaning tank inlet pipeline, 7-inlet electric valve, 8-waste gas cleaning tank outlet pipeline, 9-outlet electric valve, 10-exhaust outlet, 11-waste gas inlet electric valve, 12-marine nuclear power platform and 13-sea level.
Detailed Description
The embodiment of the invention provides a radioactive waste gas discharge system suitable for an ocean nuclear power platform, which is characterized in that low-level waste gas is cleaned by cleaning solution in a cleaning box 1 and then discharged to the external environment, so that the activity of radioactivity entering the atmosphere is further reduced, and the risk of damage to the ocean ecology is reduced.
In order to make the objects, technical solutions and advantages of the embodiments of the present application clearer, the technical solutions in the embodiments of the present application will be clearly and completely described below with reference to the drawings in the embodiments of the present application, and it is obvious that the described embodiments are some embodiments of the present application, but not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present application.
Referring to fig. 1, a radioactive exhaust emission system suitable for an ocean nuclear power platform according to an embodiment of the present invention includes an exhaust gas cleaning and collecting assembly and an exhaust emission assembly.
Waste gas cleaning and collection subassembly including wasing case 1 and loading in wasing case 1 and be used for carrying out abluent cleaning solution to low waste gas of putting, offer on the outer wall of wasing case 1 and be used for wasing the access & exit that cleaning solution changed in case 1. The cleaning solution in the embodiment of the invention is water.
Specifically, the inlet and outlet include a waste gas cleaning tank inlet 4 for introducing a cleaning solution into the cleaning tank 1, and a waste gas cleaning tank outlet 5 for discharging the cleaning solution cleaned in the cleaning tank 1. The waste gas cleaning tank inlet 4 is located at the upper portion of one side surface of the cleaning tank 1, and a waste gas cleaning tank inlet pipeline 6 is installed on the waste gas cleaning tank inlet 4. The waste gas cleaning tank inlet pipeline 6 is connected with the cleaning tank 1 and is close to the upper part of the cleaning tank 1, and clean water flows into the cleaning tank 1 through the waste gas cleaning tank inlet pipeline 6 and the waste gas cleaning tank inlet 4. An inlet electric valve 7 is arranged on an inlet pipeline 6 of the waste gas cleaning box. The inlet electric valve 7 is normally closed, when the nuclide in the water in the cleaning tank 1 is accumulated to a certain concentration, the cleaning tank 1 is emptied, then the inlet electric valve 7 is opened, and clean water is led into the cleaning tank 1 through the inlet pipeline 6 of the waste gas cleaning tank.
The waste gas cleaning tank outlet 5 is located at the bottom of the cleaning tank 1, and a waste gas cleaning tank outlet pipeline 8 is installed on the waste gas cleaning tank outlet 5. When the nuclide of the water in the cleaning tank 1 is accumulated to a certain concentration, the water in the cleaning tank 1 is discharged through an outlet pipeline 8 of the waste gas cleaning tank. An outlet electric valve 9 is arranged on an outlet pipeline 8 of the waste gas cleaning box. The outlet electro valve 9 is normally closed and is opened when required.
The rear of the waste gas cleaning box outlet pipeline 8 is connected with a collecting box, one end of the waste gas cleaning box outlet pipeline 8 is connected with the waste gas cleaning box outlet 5, and the other end of the waste gas cleaning box outlet pipeline is connected with the collecting box. Wash 1 inside medium of case and originally be clean water, clean water flows in through exhaust-gas cleaning case entry pipeline 6 and washs 1 in the case, washs and contains the water of radionuclide after the low waste gas of putting and flows to the collecting box through exhaust-gas cleaning case export 5 and exhaust-gas cleaning case exit line 8.
The waste gas discharging assembly comprises a waste gas inlet pipeline 2 arranged on the side wall of the cleaning box 1 and used for guiding low-level waste gas into the cleaning box 1, and a waste gas discharging outlet pipeline 3 arranged at the top end of the cleaning box 1 and used for discharging the cleaned low-level waste gas. The waste gas inlet pipeline 2 is positioned below one side wall of the cleaning box 1, and the treated low-radioactivity waste gas of the compartments of the nuclear power platform enters the cleaning box 1 through the waste gas inlet pipeline 2 to be cleaned. The waste gas inlet pipeline 2 is partially extended into the cleaning box 1, the other part of the waste gas inlet pipeline is positioned outside the cleaning box 1, the waste gas inlet pipeline 2 is partially extended into the cleaning box 1 and is provided with a plurality of upward exhaust outlets 10, the exhaust outlets 10 are arranged at intervals, and the waste gas inlet pipeline 2 is positioned outside the cleaning box 1 and is provided with a waste gas inlet electric valve 11. The exhaust gas inlet electric valve 11 is normally closed and is opened when necessary.
The exhaust outlets 10 are arranged on the part of the waste gas inlet pipeline 2 extending into the cleaning box 1, so that low-level waste gas entering the cleaning box 1 through the waste gas inlet pipeline 2 is uniformly distributed in the cleaning box 1, the aerosol and iodine contained in the low-level waste gas can be cleaned better, and the cleaned low-level waste gas enters the external environment through the waste gas exhaust outlet pipeline 3 and is exhausted. The cleaned low-level waste gas is discharged through the waste gas discharge outlet pipeline 3 and directly enters the external environment, and because water has a good cleaning effect on the aerosol and the iodine, the aerosol and the iodine finally discharged into the external environment can be ignored, and nuclides entering the external atmosphere only have inert gases.
The operation of the radioactive exhaust gas discharge system according to the embodiment of the present invention will be specifically described below.
The method comprises the steps of firstly leading the low-emission waste gas into a clean water quality cleaning box 1 through a waste gas cleaning box inlet pipeline 6 to enable the cleaning box 1 to be filled with clean water, opening a waste gas inlet electric valve 11 when the low-emission waste gas in each cabin needs to be discharged into the external atmosphere, enabling the low-emission waste gas to enter the cleaning box 1 through a waste gas inlet pipeline 2, enabling the water in the cleaning box 1 to clean the aerosol and iodine in the low-emission waste gas due to the good cleaning effect of the water on the aerosol and the iodine, enabling the cleaned low-emission waste gas to enter the external atmosphere through a waste gas discharge outlet pipeline 3, enabling the nuclides of the aerosol and the iodine in the cleaned low-emission waste gas to be negligible, enabling the nuclides entering the external atmosphere to be only inert gas, greatly reducing the activity of the nuclides entering the external environment, and reducing the risk.
According to the radioactive waste gas discharge system provided by the embodiment of the invention, the cleaning solution is arranged in the cleaning box 1, low-level waste gas to be cleaned is guided to the cleaning box 1 through the waste gas inlet pipeline 2, aerosol and iodine in the low-level waste gas are cleaned, the cleaned low-level waste gas enters the external atmosphere through the waste gas discharge outlet pipeline 3, namely the low-level waste gas is cleaned and then discharged to the external environment, the nuclides of the aerosol and iodine in the cleaned low-level waste gas are negligible, and the nuclides entering the external atmosphere only contain inert gas, so that the nuclides activity entering the external environment is greatly reduced, and the risk of marine ecological damage is reduced.
In the description of the present application, it should be noted that the terms "upper", "lower", and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, which are only for convenience in describing the present application and simplifying the description, and do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and operate, and thus, should not be construed as limiting the present application. Unless expressly stated or limited otherwise, the terms "mounted," "connected," and "connected" are intended to be inclusive and mean, for example, that they may be fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in the present application can be understood by those of ordinary skill in the art as appropriate.
It is noted that, in the present application, relational terms such as "first" and "second", and the like, are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Also, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising an … …" does not exclude the presence of other identical elements in a process, method, article, or apparatus that comprises the element.
The above description is merely exemplary of the present application and is presented to enable those skilled in the art to understand and practice the present application. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the application. Thus, the present application is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (10)
1. A radioactive exhaust emission system suitable for use with an offshore nuclear power platform, comprising:
the waste gas cleaning and collecting assembly comprises a cleaning box (1) and cleaning solution loaded in the cleaning box (1) and used for cleaning low-level waste gas, and an inlet and an outlet for replacing the cleaning solution in the cleaning box (1) are formed in the outer wall of the cleaning box (1);
the waste gas discharging component comprises a waste gas inlet pipeline (2) arranged on the side wall of the cleaning box (1) and used for guiding low-emission waste gas into the cleaning box (1), and a waste gas discharging outlet pipeline (3) arranged at the top end of the cleaning box (1) and used for discharging the cleaned low-emission waste gas.
2. A radioactive exhaust emission system suitable for use in an offshore nuclear power platform, according to claim 1, wherein: the inlet and the outlet comprise a waste gas cleaning box inlet (4) for leading in cleaning solution to the cleaning box (1) and a waste gas cleaning box outlet (5) for leading out the cleaning solution cleaned in the cleaning box (1).
3. A radioactive exhaust emission system suitable for use in an offshore nuclear power platform, according to claim 2, wherein: the waste gas cleaning box inlet (4) is located on the upper portion of one side face of the cleaning box (1), and a waste gas cleaning box inlet pipeline (6) is installed on the waste gas cleaning box inlet (4).
4. A radioactive exhaust emission system suitable for use in an offshore nuclear power platform, according to claim 3, wherein: an inlet electric valve (7) is arranged on an inlet pipeline (6) of the waste gas cleaning box.
5. A radioactive exhaust emission system suitable for use in an offshore nuclear power platform, according to claim 2, wherein: the waste gas cleaning box outlet (5) is located at the bottom of the cleaning box (1), and a waste gas cleaning box outlet pipeline (8) is installed on the waste gas cleaning box outlet (5).
6. The radioactive exhaust emission system for a marine nuclear power platform, according to claim 5, wherein: the rear part of the waste gas cleaning box outlet pipeline (8) is connected with a collecting box, one end of the waste gas cleaning box outlet pipeline (8) is connected with a waste gas cleaning box outlet (5), and the other end of the waste gas cleaning box outlet pipeline is connected with the collecting box.
7. The radioactive exhaust emission system for a marine nuclear power platform, according to claim 5, wherein: an outlet electric valve (9) is arranged on an outlet pipeline (8) of the waste gas cleaning box.
8. A radioactive exhaust emission system suitable for use in an offshore nuclear power platform, according to claim 1, wherein: the waste gas inlet pipeline (2) is positioned below one side wall of the cleaning box (1).
9. The radioactive exhaust emission system for a marine nuclear power platform, according to claim 8, wherein: waste gas entry pipeline (2) partly stretch into wash in case (1), another part is located outside washing case (1), and waste gas entry pipeline (2) stretch into and wash and seted up a plurality of ascending exhaust outlets (10) on the part in case (1), and a plurality of exhaust outlets (10) are the interval setting, and waste gas entry pipeline (2) are located and are provided with waste gas entry motorised valve (11) on the part outside washing case (1).
10. A radioactive exhaust emission system suitable for use in a marine nuclear power platform according to any one of claims 1 to 9, wherein: the cleaning solution is water.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010755174.4A CN111744334A (en) | 2020-07-31 | 2020-07-31 | Radioactive waste gas discharge system suitable for ocean nuclear power platform |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010755174.4A CN111744334A (en) | 2020-07-31 | 2020-07-31 | Radioactive waste gas discharge system suitable for ocean nuclear power platform |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN111744334A true CN111744334A (en) | 2020-10-09 |
Family
ID=72712458
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010755174.4A Pending CN111744334A (en) | 2020-07-31 | 2020-07-31 | Radioactive waste gas discharge system suitable for ocean nuclear power platform |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111744334A (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2074893A (en) * | 1980-05-02 | 1981-11-11 | Us Energy | Passive self-cleaning aerosol scrubber |
| CN202855323U (en) * | 2012-09-11 | 2013-04-03 | 中科华核电技术研究院有限公司 | Filtering and gathering system and steam and atmosphere discharging system |
| CN104078085A (en) * | 2014-06-04 | 2014-10-01 | 中国核电工程有限公司 | Containment built-in refueling water tank with washing function |
| US20150314240A1 (en) * | 2014-05-05 | 2015-11-05 | Ge-Hitachi Nuclear Energy Americas Llc | Salt filtration system and method of removing a radioactive material from a gas using the same |
| CN210167124U (en) * | 2019-05-23 | 2020-03-20 | 中国核电工程有限公司 | Containment pressure relief and filtration system |
-
2020
- 2020-07-31 CN CN202010755174.4A patent/CN111744334A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2074893A (en) * | 1980-05-02 | 1981-11-11 | Us Energy | Passive self-cleaning aerosol scrubber |
| CN202855323U (en) * | 2012-09-11 | 2013-04-03 | 中科华核电技术研究院有限公司 | Filtering and gathering system and steam and atmosphere discharging system |
| US20150314240A1 (en) * | 2014-05-05 | 2015-11-05 | Ge-Hitachi Nuclear Energy Americas Llc | Salt filtration system and method of removing a radioactive material from a gas using the same |
| CN104078085A (en) * | 2014-06-04 | 2014-10-01 | 中国核电工程有限公司 | Containment built-in refueling water tank with washing function |
| CN210167124U (en) * | 2019-05-23 | 2020-03-20 | 中国核电工程有限公司 | Containment pressure relief and filtration system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104412328B (en) | Filter for a nuclear reactor containment ventilation system | |
| CN108885909B (en) | Inter-module fuel switching | |
| CN104157318B (en) | Nuclear power station hydrogeneous Spent Radioactive gas processing system | |
| CN107833644A (en) | The refuelling system and material-changing method of ocean nuclear power platform | |
| US20050069074A1 (en) | Nuclear plant spent fuel low temperature reactor | |
| WO2020248530A1 (en) | Nuclear power plant containment filtering and discharging system and method | |
| CN107180661A (en) | A kind of spent fuel transport container residual heat removal facility | |
| JP2023123623A (en) | Double standard fuel canister system | |
| CN111744334A (en) | Radioactive waste gas discharge system suitable for ocean nuclear power platform | |
| CN1316506C (en) | Deep water tank nuclear heat supply reactor adopting waste fuel of nuclear power station | |
| CN107665745A (en) | A kind of high storage container for putting detector assembly | |
| JP5823902B2 (en) | Method for transporting spent fuel in nuclear power plants | |
| CN207425376U (en) | The refuelling system of ocean nuclear power platform | |
| CN108421411A (en) | Distributed photocatalytic waste gas treatment device based on photoelectric conversion and its application method | |
| CN115295199A (en) | Hydrogen-containing radioactive waste gas treatment system and method for nuclear power plant | |
| JP2015064306A (en) | Spent nuclear fuel assembly transport method and spent nuclear fuel assembly transport cask | |
| CN109273127A (en) | The method of nuclear power plant's prefilter frame recycling | |
| JP2011237293A (en) | Radioactive material storage method | |
| CN201166993Y (en) | Bucket type protecting device for feeding charge into a neutron source stick | |
| CN217238399U (en) | Pretreatment device for analyzing carbon-14 activity in high-activity tritium water | |
| US20220102019A1 (en) | Chemical decontamination method | |
| RU64425U1 (en) | SYSTEM OF CLEANING WORKING CARTRIDGES OF THE NUCLEAR REACTOR TYPE VVER-440 | |
| CN116562047A (en) | Radioactive source item calculation method, device and evaluation method of control body | |
| KR101149552B1 (en) | Lacquer coating apparatus for nuclear fuel rod assembly with improved exhausting gas pipe | |
| CN115171933A (en) | Volume reduction treatment system and treatment method for radioactive waste oil of pressurized water reactor nuclear power plant |
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 | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20201009 |