CN109637684B - Underground nuclear power plant with low-medium level radioactive waste disposal system and disposal method thereof - Google Patents
Underground nuclear power plant with low-medium level radioactive waste disposal system and disposal method thereof Download PDFInfo
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- CN109637684B CN109637684B CN201811613089.3A CN201811613089A CN109637684B CN 109637684 B CN109637684 B CN 109637684B CN 201811613089 A CN201811613089 A CN 201811613089A CN 109637684 B CN109637684 B CN 109637684B
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- 239000002901 radioactive waste Substances 0.000 title claims abstract description 34
- 238000000034 method Methods 0.000 title claims abstract description 30
- 239000002699 waste material Substances 0.000 claims abstract description 318
- 238000010248 power generation Methods 0.000 claims abstract description 50
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 41
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 29
- 239000002925 low-level radioactive waste Substances 0.000 claims abstract description 24
- 238000012546 transfer Methods 0.000 claims abstract description 22
- 239000002351 wastewater Substances 0.000 claims abstract description 18
- 239000007788 liquid Substances 0.000 claims description 156
- 239000007789 gas Substances 0.000 claims description 37
- 208000028659 discharge Diseases 0.000 claims description 31
- 239000002912 waste gas Substances 0.000 claims description 23
- 238000001514 detection method Methods 0.000 claims description 21
- 239000002910 solid waste Substances 0.000 claims description 20
- 238000005070 sampling Methods 0.000 claims description 17
- 238000009423 ventilation Methods 0.000 claims description 16
- 239000000446 fuel Substances 0.000 claims description 15
- 230000002285 radioactive effect Effects 0.000 claims description 15
- 229910000831 Steel Inorganic materials 0.000 claims description 13
- 238000001035 drying Methods 0.000 claims description 13
- 239000010959 steel Substances 0.000 claims description 13
- 239000010808 liquid waste Substances 0.000 claims description 11
- 150000003839 salts Chemical class 0.000 claims description 10
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 9
- 230000000694 effects Effects 0.000 claims description 8
- 238000005342 ion exchange Methods 0.000 claims description 7
- 239000002354 radioactive wastewater Substances 0.000 claims description 6
- 238000000926 separation method Methods 0.000 claims description 6
- 229910052799 carbon Inorganic materials 0.000 claims description 5
- 238000001914 filtration Methods 0.000 claims description 5
- 238000010438 heat treatment Methods 0.000 claims description 5
- 238000012545 processing Methods 0.000 claims description 5
- 238000012544 monitoring process Methods 0.000 claims description 4
- 239000000941 radioactive substance Substances 0.000 claims description 4
- 238000001179 sorption measurement Methods 0.000 claims description 4
- 239000000126 substance Substances 0.000 claims description 4
- 239000002894 chemical waste Substances 0.000 claims description 3
- 238000010612 desalination reaction Methods 0.000 claims description 3
- 238000001704 evaporation Methods 0.000 claims description 3
- 230000008020 evaporation Effects 0.000 claims description 3
- 239000000706 filtrate Substances 0.000 claims description 3
- 238000007711 solidification Methods 0.000 claims description 3
- 230000008023 solidification Effects 0.000 claims description 3
- 238000005516 engineering process Methods 0.000 claims description 2
- 230000002209 hydrophobic effect Effects 0.000 claims description 2
- 238000004806 packaging method and process Methods 0.000 claims description 2
- 125000004122 cyclic group Chemical group 0.000 claims 1
- 239000003657 drainage water Substances 0.000 claims 1
- 238000009412 basement excavation Methods 0.000 abstract description 5
- 238000005192 partition Methods 0.000 description 3
- 230000001681 protective effect Effects 0.000 description 3
- 238000009270 solid waste treatment Methods 0.000 description 3
- 238000010276 construction Methods 0.000 description 2
- 238000011033 desalting Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 239000011347 resin Substances 0.000 description 2
- 229920005989 resin Polymers 0.000 description 2
- 238000004065 wastewater treatment Methods 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000011435 rock Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
-
- 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
-
- 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
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/22—Disposal of liquid waste by storage in a tank or other container
-
- 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
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
-
- 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
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Environmental & Geological Engineering (AREA)
- Plasma & Fusion (AREA)
- Measurement Of Radiation (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
The utility model relates to the technical field of underground nuclear power stations and discloses an underground nuclear power station with a low-medium level waste disposal system, which comprises a power generation area and a waste disposal area, wherein the power generation area comprises a plurality of single-pile nuclear power systems, each single-pile nuclear power system comprises a plurality of plants, the waste disposal area comprises SRTF field site waste disposal facilities, the SRTF field waste disposal facilities are connected with a power generation area traffic tunnel through waste transfer tunnels, a drain water tank communicated with a field waste water drain system of the power generation area is arranged at the bottom of the SRTF field waste disposal facilities, and the SRTF field waste disposal facilities are also connected with a low-level waste disposal tunnel, a medium-level waste disposal tunnel and a spent fuel dry storage area. The utility model also discloses a disposal method of the underground nuclear power plant with the low-medium level waste disposal system. The underground nuclear power station with the low-medium level waste disposal system and the disposal method thereof realize centralization of waste disposal function while solving the problem of site selection of the low-medium level waste disposal system, reduce excavation of a grotto and avoid the problem of nuclear security in the process of outward transportation of radioactive waste.
Description
Technical Field
The utility model relates to the technical field of underground nuclear power stations, in particular to an underground nuclear power station with a low-medium level waste disposal system and a disposal method thereof.
Background
With the development of nuclear power in China, more and more radioactive wastes are generated in nuclear power plants, and the treatment and disposal of the radioactive wastes become important factors for restricting the long-term sustainable development of the nuclear power in China.
The primary forms of low and medium radioactive waste generated by the operation of nuclear power plants are radioactive wastewater, exhaust gas and solid waste. Wherein the radioactive wastewater comprises process wastewater, chemical wastewater and ground wastewater; the exhaust gas includes hydrogen-containing exhaust gas and hydrogen-free exhaust gas; the solid waste includes vapor residue concentrate, radioactive waste resin, filter cartridges, HVAC cartridges, and other radioactive solid impurities.
The method for treating the radioactive waste in the domestic nuclear power plant mainly comprises two modes, namely a single-pile treatment mode, wherein the cured waste is temporarily stored in a waste temporary warehouse in a field; another type of radioactive waste generated by the operation of the nuclear power plant is transferred to a site waste treatment facility (SRTF) in a field area through an auxiliary plant and a waste discharge plant for centralized treatment, single-heap treatment is not carried out any more, the SRTF is taken as a BOP sub-item in the field area, the cured and prepared radioactive solid waste is temporarily stored, and the radioactive solid waste generated by 6 AP1000 units is taken as an example, and is slightly 50m each year 3 The SRTF temporary storage has a storage space of 5 years, and the SRTF is far away from the nuclear island area, so that radiation protection is facilitated.
At present, a mode of centralized disposal is adopted for low-medium radioactive solid wastes of each nuclear power plant in China, and two low-medium near-surface waste disposal sites of Gansu northwest and Guangdong northwest are built in China, wherein the disposal depth is 0-30 meters; at present, a karst cave treatment mode is adopted in a Guangdong Yangjiang low-middle-level disposal place with a disposal depth of 30-300 meters.
The underground nuclear power station places nuclear-related plants such as a nuclear island and the like underground, the radioactive substances are limited to be released to the external environment under the severe accident working condition by utilizing the containing capacity of the rock mass, the safety is high, the bottom elevation of main plants such as the reactor plant is about 200 meters underground, and the bottom elevation of the main plants is close to the treatment depth of a karst cave type low-medium-level treatment field.
The low-medium level waste treatment and disposal facilities of the ground nuclear power plant adopt a separation arrangement mode, and in the current conceptual design of the underground nuclear power plant, the low-medium level waste treatment scheme is still to treat in a nuclear island, and the prepared waste is transported to a ground waste disposal site. Because the plant depth of the underground nuclear power plant is close to the treatment depth of a cave-type low-medium-level treatment field, the site selection conditions are similar, and the underground nuclear power plant and the cave-type low-medium-level treatment field can be uniformly arranged.
The Chinese patent application (publication date: 18 of 1 of 2017 and publication number: CN 205900109U) discloses an underground nuclear power plant with a low-medium radioactive waste disposal site, and the underground nuclear power plant and the low-medium radioactive waste disposal site are integrally arranged, so that unified planning and construction of the nuclear power plant and the disposal site are realized, the cost is saved, but a treatment scheme of low-medium radioactive waste and an interface design of treatment and disposal are lacked.
Disclosure of Invention
The utility model aims at overcoming the defects of the technology, and provides an underground nuclear power plant with a low-medium level waste disposal system and a disposal method thereof, which solve the problem of site selection of the low-medium level waste disposal site, realize centralization of waste disposal function, reduce excavation of a grotto and avoid nuclear security problem in the process of outward transportation of radioactive waste.
In order to achieve the above object, the underground nuclear power plant with the low-medium level waste disposal system comprises a power generation area positioned in a underground cavity and a waste disposal area positioned inside the underground cavity, wherein the power generation area comprises a plurality of single-pile nuclear power systems, each single-pile nuclear power system comprises a reactor plant, a fuel plant, an electric plant and a nuclear auxiliary plant, the fuel plant, the electric plant and the nuclear auxiliary plant are all connected with a power generation area traffic tunnel, the reactor plant is connected with the fuel plant and the electric plant, the waste disposal area comprises an SRTF (SRTF) site waste disposal facility, the SRTF site waste disposal facility is connected with the power generation area traffic tunnel through at least one waste transfer tunnel, a drain flume communicated with a field waste water drain system of the power generation area is arranged at the bottom of the waste transfer tunnel, and the SRTF site waste disposal facility is also connected with a low-level waste disposal tunnel, a medium level waste disposal dry type storage area and a fuel dry type storage area through the waste disposal area.
Preferably, each factory building of single nuclear power system is L type and arranges, low radioactive waste disposal tunnel is located the back surface of SRTF place waste disposal facility is inboard, well radioactive waste disposal tunnel and spent fuel dry-type storage area all are located the back surface of low radioactive waste disposal tunnel is inboard, be equipped with radioactive waste gas processing apparatus and radioactive waste liquid and solid waste collection device in the nuclear auxiliary factory building, SRTF place waste disposal facility includes the waste disposal factory building, the waste disposal factory building includes the storage the hydrophobic waste liquid temporary storage tank of SRTF place waste disposal facility, stores No. two waste liquid temporary storage tanks of low radioactive waste disposal tunnel and well radioactive waste disposal tunnel drainage and the waste liquid transport container of the waste water that power generation district process waste water, chemical waste water, ground hydrophobicity and radioactive waste liquid and solid waste collection device collected, no. one waste liquid temporary storage tank, no. two waste liquid temporary storage tanks and waste liquid transport container all are equipped with sample detection device.
Preferably, the first waste liquid temporary storage tank, the second waste liquid temporary storage tank and the waste liquid transfer container are all connected with a first waste liquid treatment device, the first waste liquid treatment device comprises a first filter, a preheater, an evaporator, a steam-water separator, a cooler, a desalting bed and a distilled liquid storage tank which are sequentially connected, the evaporator is connected with a waste drying steel drum, the distilled liquid storage tank is connected with a discharge water tank, and the distilled liquid storage tank is provided with a waste liquid sampling and detecting device.
Preferably, the first waste liquid temporary storage tank, the second waste liquid temporary storage tank and the waste liquid transfer container are all connected with a second waste liquid treatment device, the second waste liquid treatment device comprises a second filter and an ion exchange column which are sequentially connected, an outlet of the second waste liquid treatment device is connected with the discharge water tank, and a waste liquid sampling and detecting device is arranged at the tail end of the second waste liquid treatment device.
Preferably, the waste treatment plant further comprises a first gas collecting device for collecting the gas-borne radioactive effluent of the SRTF site waste discharge treatment facility and a second gas collecting device for collecting the gas-borne radioactive effluent of the low-level waste treatment tunnel, the medium-level waste treatment tunnel and the spent fuel dry storage area, wherein the first gas collecting device and the second gas collecting device are both connected with a waste gas treatment device, the waste gas treatment device comprises a gas-liquid separator, an active carbon protective bed, a first-stage delay bed and a second-stage delay bed which are sequentially connected, the tail end of the waste gas treatment device is provided with a waste gas detection device, the outlet of the waste gas treatment device is communicated with a ventilation shaft at the top of the waste treatment plant, and the gas-liquid separator is communicated with the first waste liquid temporary storage tank.
Preferably, the spent fuel dry storage area is located at one side of the medium-level waste disposal tunnel, a concrete partition wall is arranged between the medium-level waste disposal tunnel and the spent fuel dry storage area, the spent fuel dry storage area is provided with a radiating ventilation system, the SRTF site waste disposal treatment facility is provided with a laundry, and the waste treatment plant is arranged in multiple layers and comprises a process treatment area, an auxiliary process area, a control area, a heating ventilation room and an electrical instrument control plant.
The disposal method of the underground nuclear power plant with the low-medium level waste disposal system comprises the steps that an SRTF site waste disposal facility collects and processes radioactive wastewater from a power generation area, an SRTF site waste disposal facility, a low-level waste disposal tunnel, a medium-level waste disposal tunnel and a spent fuel dry storage area, an evaporation concentration residual liquid is barreled and solidified, and distilled liquid and low-level filtrate are subjected to tank monitoring and discharge through a discharge water tank after being subjected to sampling detection; the SRTF site waste disposal facility carries out gas-liquid separation and adsorption filtration on the gas-borne radioactive effluents of the SRTF site waste disposal facility, the low-level waste disposal tunnel, the medium-level waste disposal tunnel and the spent fuel dry storage area, and the gas-borne radioactive effluents are discharged to the ventilation shaft after being detected to be qualified; the SRTF site waste disposal facility is used for processing, sorting, solidifying and packaging the waste drying steel drum subjected to waste liquid treatment and the low-medium level solid waste from the power generation area, and respectively conveying the waste drying steel drum to the low-level waste disposal tunnel and the medium-level waste disposal tunnel for final disposal according to the activity of radioactive substances in the waste drum; the spent fuel dry storage area temporarily stores spent fuel which decays and releases heat from the fuel factory during the operation of the power generation area, and the spent fuel is transported to the ground through the waste transport tunnel and the power generation area traffic tunnel by a special transport container after the spent fuel dry storage area is piled up.
Preferably, after the waste liquid in the first waste liquid temporary storage tank, the second waste liquid temporary storage tank and the waste liquid transferring container is sampled and detected, the radioactivity and the chemical salt content of the waste liquid are obtained, when the waste liquid is high in salt content and high in activity, the waste liquid passes through the first waste liquid treatment device, is filtered by the first filter and is heated by the preheater, then enters the evaporator, the evaporated and concentrated solution is injected into the waste drying steel drum for solidification treatment, the distilled solution is subjected to steam-water separation by the steam-water separator, the steam re-enters the evaporator, the distilled solution enters the distilled solution storage tank for storage after passing through the cooler and the salt removal bed, and the waste liquid which is qualified in sampling and detection is led to a field waste water discharge system of the power generation area to be discharged outside the field through the discharge water tank; when the waste liquid is low in salt and activity, the waste liquid passes through the second waste liquid treatment device, is filtered by the second filter, passes through the ion exchange column, is properly discharged to the discharge water tank through sampling detection, and is discharged out of the field waste water discharge system of the power generation area.
Preferably, after the waste gas collected by the first gas collecting device and the second gas collecting device passes through the gas-liquid separator, the separated waste liquid enters the first waste liquid temporary storage tank, the waste gas is adsorbed and filtered by the active carbon protection bed, the first-stage delay bed and the second-stage delay bed, and is discharged to a ventilation vertical shaft after being detected to be qualified by the waste gas detecting device, and the waste gas which is detected to be unqualified is subjected to circulation treatment.
Compared with the prior art, the utility model has the following advantages:
1. the underground nuclear power plant and the low-medium-level disposal site are uniformly arranged and subjected to uniform site selection, so that the three-simultaneous principle that the disposal site and the nuclear power plant are designed, constructed and put into use simultaneously is realized, the site selection problem of the low-medium-level disposal site is solved, site resources are saved, near-field disposal of low-medium-level waste is realized, and the construction economy of the underground nuclear power plant can be greatly improved;
2. the waste liquid and solid waste treatment functions of the nuclear auxiliary factory building of the conventional nuclear power plant nuclear island are stripped, the waste treatment factory building and temporary storage factory building of the nuclear island are eliminated, and the waste treatment facilities of the SRTF site are planned to carry out unified treatment, so that the overlapping of the waste treatment functions of the multiple factory buildings is avoided;
3. arranging the waste treatment plant, the low-level waste treatment tunnel and the medium-level waste treatment tunnel nearby, wherein the solidified waste produced by the waste treatment plant can be directly transferred to the treatment tunnel, so that a waste temporary storage room in an SRTF plant of the AP1000 can be canceled, and the space of the SRTF plant and the excavation amount of a cavity are reduced;
4. the low-medium level waste produced during the 60-year operation of the nuclear power plant can be subjected to real-time monitoring through a waste liquid sampling and detecting device and an exhaust gas detecting device of a waste treatment plant after final treatment in a waste treatment area, and the airborne radioactivity and radioactive wastewater can be collected and treated;
5. the spent fuel dry storage area can be used for carrying out centralized and long-term storage on the spent fuel generated by the nuclear island of the whole plant area, so that the dilemma that the spent fuel pool of the ground nuclear power plant is full and the spent fuel is not stacked is solved;
6. by uniformly arranging the power generation area and the waste disposal area, the waste is disposed nearby, so that the nuclear security problem possibly existing in the process of transporting the low-medium level waste of the ground nuclear power station is avoided.
Drawings
FIG. 1 is a schematic plan view of an underground nuclear power plant with a low-medium level waste disposal system of the present utility model;
FIG. 2 is a schematic view of a waste liquid treatment apparatus in an underground nuclear power plant with a low-medium level waste disposal system according to the present utility model;
fig. 3 is a schematic structural view of an exhaust gas treatment apparatus in an underground nuclear power plant having a low-medium level waste disposal system according to the present utility model.
The reference numerals of the components in the drawings are as follows:
the power generation area 1, the single-stack nuclear power system 11, the reactor plant 111, the fuel plant 112, the electric plant 113, the nuclear auxiliary plant 114, the power generation area traffic tunnel 12, the waste disposal area 2, the SRTF site effluent disposal facility 21, the waste transfer tunnel 22, the waste disposal area traffic tunnel 23, the low level waste disposal tunnel 24, the medium level waste disposal tunnel 25, the spent fuel dry storage area 26, the concrete partition 27, the first waste liquid temporary storage tank A1, the second waste liquid temporary storage tank A2, the waste liquid transfer container A3, the first filter A4, the preheater A5, the evaporator A6, the steam-water separator A7, the cooler A8, the desalination bed A9, the distillate storage tank a10, the waste drying steel drum a11, the discharge water tank a12, the second filter a13, the ion exchange column a14, the first gas collecting device B1, the second gas collecting device B2, the gas-liquid separator B3, the activated carbon protective bed B4, the first delay bed B5, the second delay bed B6, the waste gas detection device B7, and the ventilation shaft B8.
Detailed Description
The utility model will now be described in further detail with reference to the drawings and to specific examples.
As shown in fig. 1, the underground nuclear power plant with the low-medium level waste disposal system of the utility model comprises a power generation area 1 positioned in an underground cavity to realize the power generation function, and further comprises a waste disposal area 2 positioned at the inner side of the underground cavity to process and dispose the waste generated by the power generation area 1, in this embodiment, the power generation area 1 comprises two single-stack nuclear power systems 11, each single-stack nuclear power system 11 comprises a reactor plant 111, a fuel plant 112, an electric plant 113 and a nuclear auxiliary plant 114, the fuel plant 112, the electric plant 113 and the nuclear auxiliary plant 114 are all connected with a power generation area traffic tunnel 12, the reactor plant 111 is connected with the fuel plant 112, the reactor plant 111 is connected with the electric plant 113, the two single-stack nuclear power systems 11 share the power generation area traffic tunnel 12, the waste disposal area 2 comprises an SRTF site waste disposal facility 21, the SRTF site waste disposal facility 21 is connected with the power generation area traffic tunnel 12 through at least one waste transfer tunnel 22, a drain water tank A12 communicated with a field waste water drain system of the power generation area 1 is arranged at the bottom of the waste transfer tunnel 22, as shown in connection with FIG. 2, the SRTF site waste disposal facility 21 is also connected with a low-level waste disposal tunnel 24, a medium-level waste disposal tunnel 25 and a spent fuel dry storage area 26 through a waste disposal area traffic tunnel 23, the low-level waste disposal tunnel 24 and the medium-level waste disposal tunnel 25 receive solid waste barrels from the SRTF site waste disposal facility 21 through the waste disposal area traffic tunnel 23, the spent fuel dry storage area 26 is used for temporarily storing spent fuel of the whole plant area, receives the spent fuel after decay heat release in the fuel factory 112, after being piled up, the waste is transported to the ground for post-treatment or final disposal as high-level waste by a special vehicle through a waste transfer tunnel 22.
In addition, each plant of the single-pile nuclear power system 11 is L-shaped, the low-level waste disposal tunnel 24 is positioned at the inner side of the backup body of the SRTF site waste disposal facility 21, the medium-level waste disposal tunnel 25 and the spent fuel dry storage area 26 are positioned at the inner side of the backup body of the low-level waste disposal tunnel 24, the nuclear auxiliary plant 114 is internally provided with a radioactive waste gas disposal device and a radioactive waste liquid and solid waste collection device, only the radioactive waste gas disposal function of the power generation area 1 and the radioactive waste liquid and solid waste collection function are reserved, the radioactive waste liquid and solid waste disposal function is stripped, the nuclear waste plant and the waste temporary storage plant are eliminated, the plant space and the cavity excavation amount of the nuclear auxiliary plant 114 are greatly reduced, the SRTF site waste disposal facility 21 comprises the waste disposal plant, the waste temporary storage plant of the AP1000 power station SRTF is eliminated, the main functions of the waste treatment factory building are to treat radioactive waste liquid and solid waste from a factory floor power generation area 1, an SRTF site waste disposal facility 21, a low-level waste disposal tunnel 24, a medium-level waste disposal tunnel 25 and a spent fuel dry storage area 26, and are packaged in a servicing way, and the waste treatment factory building comprises a first waste liquid temporary storage tank A1 for storing the drainage of the SRTF site waste disposal facility 21, a second waste liquid temporary storage tank A2 for storing the drainage of the low-level waste disposal tunnel 24 and the medium-level waste disposal tunnel 25, and a waste liquid transfer container A3 for storing the process waste water, the chemical waste water, the ground drainage, the radioactive waste liquid and the waste water collected by a solid waste collecting device in the power generation area 1, wherein the waste liquid transfer container A3 is a movable shielding transfer container, and the first waste liquid temporary storage tank A1, the second waste liquid temporary storage tank A2 and the waste liquid transfer container A3 are all provided with waste liquid sampling detection devices.
As shown in fig. 2, a first waste liquid temporary storage tank A1, a second waste liquid temporary storage tank A2 and a waste liquid transfer container A3 are all connected with a first waste liquid treatment device, the first waste liquid treatment device comprises a first filter A4, a preheater A5, an evaporator A6, a steam-water separator A7, a cooler A8, a desalination bed A9 and a distillate storage tank a10 which are sequentially connected, the evaporator A7 is connected with a waste drying steel drum a11, the distillate storage tank a10 is connected with a discharge water tank a12, and the distillate storage tank a10 is provided with a waste liquid sampling detection device.
In addition, a waste liquid temporary storage tank A1, a second waste liquid temporary storage tank A2 and a waste liquid transfer container A3 are all connected with a second waste liquid treatment device, the second waste liquid treatment device comprises a second filter A13 and an ion exchange column A14 which are sequentially connected, an outlet of the second waste liquid treatment device is connected with a discharge water tank A12, and a waste liquid sampling and detecting device is arranged at the tail end of the second waste liquid treatment device.
As shown in fig. 3, the waste treatment plant further comprises a first gas collecting device B1 for collecting the air-borne radioactive effluent of the SRTF site waste disposal facility 21, a second gas collecting device B2 for collecting the air-borne radioactive effluent of the low-level waste disposal tunnel 24, the medium-level waste disposal tunnel 25 and the spent fuel dry storage area 26, the first gas collecting device B1 and the second gas collecting device B2 are both connected with a waste gas treatment device, the waste gas treatment device comprises a gas-liquid separator B3, an activated carbon protective bed B4, a first-stage delay bed B5 and a second-stage delay bed B6 which are sequentially connected, the tail end of the waste gas treatment device is provided with a waste gas detection device B7, the outlet of the waste gas treatment device is communicated with a ventilation shaft B8 at the top of the waste treatment plant, and the gas-liquid separator B3 is communicated with the first waste liquid temporary storage tank A1.
In this embodiment, the spent fuel dry storage area 26 is located at one side of the medium level waste disposal tunnel 25, a concrete partition wall 27 is disposed between the medium level waste disposal tunnel 25 and the spent fuel dry storage area 26, the spent fuel dry storage area 26 is provided with a heat dissipation ventilation system for dissipating heat of spent fuel, the SRTF site waste disposal facility 21 is provided with a laundry room, and the waste disposal plant is arranged in multiple layers, including a process disposal area, an auxiliary process area, a control area, a heating ventilation room and an electrical instrument control plant.
The disposal method of the underground nuclear power plant with a low-medium level waste disposal system comprises the steps that an SRTF site waste disposal facility 21 collects and processes radioactive wastewater from a power generation area 1, the SRTF site waste disposal facility 21, a low-level waste disposal tunnel 24, a medium-level waste disposal tunnel 25 and a spent fuel dry storage area 26, an evaporation concentration residual liquid is barreled and solidified, and distilled liquid and low-level filtrate are subjected to tank monitoring and discharge through a discharge tank A12 after being qualified by sampling and detection; the SRTF site waste disposal facility 21 carries out gas-liquid separation and adsorption filtration on the gas-borne radioactive effluents of the SRTF site waste disposal facility 21, the low-level waste disposal tunnel 24, the medium-level waste disposal tunnel 25 and the spent fuel dry storage area 26, and the gas-borne radioactive effluents are discharged to the ventilation shaft B8 after being detected to be qualified; the SRTF site waste disposal facility 21 processes, sorts, solidifies and packages the waste drying steel drum A11 after the waste liquid treatment and the low-medium level solid waste from the power generation region 1, and respectively conveys the waste drying steel drum A11 to the low-level waste disposal tunnel 24 and the medium-level waste disposal tunnel 25 for final disposal through the waste disposal region transportation tunnel 23 according to the activity of radioactive substances of the waste drum, wherein the solid waste source items comprise waste resin generated from the power generation region 1, filter cores, HVAC filter cores, waste liquid of a waste water treatment system, dry solid waste, other miscellaneous waste and the like, the HVAC filter cores generated by the heating and ventilation system of the SRTF site waste disposal facility 21, waste liquid of the waste water treatment from the low-level waste disposal tunnel 24 and the medium-level waste disposal tunnel 25; the spent fuel dry storage area 26 temporarily stores spent fuel after decay of heat release from the fuel plant 112 during operation of the power generation area 1, and after the spent fuel dry storage area 26 is fully stacked, the spent fuel is transported to the ground through the dedicated transport vessel via the waste transport tunnel 22 and the power generation area traffic tunnel 12.
After sampling and detecting the waste liquid in the first waste liquid temporary storage tank A1, the second waste liquid temporary storage tank A2 and the waste liquid transferring container A3, acquiring the radioactivity and chemical salt content of the waste liquid, filtering the waste liquid through a first waste liquid treatment device, heating the waste liquid through a first filter A4 and a preheater A5, then feeding the waste liquid into an evaporator A6, injecting the evaporated and concentrated liquid into a waste drying steel drum A11 for solidification treatment, separating steam from water of a distilled liquid through a steam-water separator A7, re-feeding steam into the evaporator A6, storing the distilled liquid in a distilled liquid storage tank A10 after passing through a cooler A8 and a desalting bed A9, and leading the waste liquid which is qualified in sampling and detection to the outside of a field waste water discharge system of the power generation area 1 through a discharge water tank A12; when the waste liquid is low in salt and activity, the waste liquid is filtered by the second waste liquid treatment device through the second filter A13, passes through the ion exchange column A14, is properly discharged to the discharge water tank A12 through sampling detection, and is discharged out of the field waste water discharge system of the power generation area 1.
After the waste gas collected by the first gas collecting device B1 and the second gas collecting device B2 passes through the gas-liquid separator B3, the separated waste liquid enters the first waste liquid temporary storage tank A1, the waste gas is adsorbed and filtered by the active carbon protection bed B4, the first-stage delay bed B5 and the second-stage delay bed B6, and is discharged to the ventilation vertical shaft B8 after being detected to be qualified by the waste gas detection device B7, and the waste gas which is detected to be unqualified is subjected to circulation treatment.
The underground nuclear power plant with the low-medium level waste disposal system and the disposal method thereof solve the problem of site selection of the low-medium level disposal site by uniformly arranging the underground nuclear power plant and the low-medium level disposal site; the waste liquid and solid waste treatment function of the nuclear island area of the nuclear power station is stripped, and the waste liquid and solid waste treatment facility is transported to the SRTF site of the waste treatment area for centralized treatment and then is treated on site, so that the centralized waste treatment function is realized, a waste temporary storage factory is not required to be arranged independently, the excavation of a grotto is reduced, the nuclear security problem in the outward transportation process of radioactive waste is avoided, and the overall economy is good.
Claims (8)
1. An underground nuclear power plant with a low-medium level waste disposal system comprising a power generation zone (1) located in an underground cavity, characterized in that: the system further comprises a waste disposal area (2) positioned inside the underground cavity, the power generation area (1) comprises a plurality of single-pile nuclear power systems (11), each single-pile nuclear power system (11) comprises a reactor plant (111), a fuel plant (112), an electric plant (113) and a nuclear auxiliary plant (114), the fuel plant (112), the electric plant (113) and the nuclear auxiliary plant (114) are all connected with a power generation area traffic tunnel (12), the reactor plant (111) is connected with the fuel plant (112) and the electric plant (113), the waste disposal area (2) comprises SRTF site waste disposal facilities (21), the SRTF site waste disposal facilities (21) are connected with the power generation area traffic tunnel (12) through at least one waste transfer tunnel (22), the bottom of the waste transfer tunnel (22) is provided with a drainage water tank (A12) communicated with a field waste drainage system of the power generation area (1), the SRTF site waste disposal facilities (21) are also connected with waste disposal areas (24) in a low-level waste (25) through a single-pile tunnel (23), the single-pile waste disposal area (25) and the single-pile waste disposal area (25), the utility model provides a waste liquid transfer container (A3) of waste liquid that is equipped with radioactive waste gas treatment device and radioactive waste liquid and solid waste collection device in nuclear auxiliary factory building (114), SRTF site waste liquid treatment facility (21) includes the waste treatment factory building, the waste treatment factory building includes the storage the waste liquid temporary storage tank (A1) of SRTF site waste liquid treatment facility (21) hydrophobic No. one, stores waste liquid temporary storage tank (A2) of low-level waste treatment tunnel (24) and well waste liquid treatment tunnel (25) drainage and storage waste liquid transfer container (A3) of waste liquid that power generation zone (1) technology waste water, chemical waste water, ground hydrophobicity and radioactive waste liquid and solid waste collection device collected, waste liquid temporary storage tank (A1), no. two waste liquid temporary storage tank (A2) and waste liquid transfer container (A3) are equipped with sample waste liquid.
2. The underground nuclear power plant with a low-medium level waste disposal system of claim 1, wherein: waste liquid temporary storage tank (A1), no. two waste liquid temporary storage tank (A2) and waste liquid transport container (A3) all link to have a waste liquid processing apparatus, a waste liquid processing apparatus is including a filter (A4), pre-heater (A5), evaporimeter (A6), vapour-water separator (A7), cooler (A8), desalination bed (A9) and distillate storage tank (A10) that connect gradually, evaporimeter (A6) even has waste drying steel drum (A11), distillate storage tank (A10) even has discharge flume (A12), distillate storage tank (A10) are equipped with waste liquid sample detection device.
3. The underground nuclear power plant with a low-medium level waste disposal system of claim 2, wherein: the waste liquid temporary storage tank (A1), the waste liquid temporary storage tank (A2) and the waste liquid transfer container (A3) are all connected with a waste liquid treatment device, the waste liquid treatment device comprises a second filter (A13) and an ion exchange column (A14) which are sequentially connected, the outlet of the second waste liquid treatment device is connected with the discharge water tank (A12), and the tail end of the second waste liquid treatment device is provided with a waste liquid sampling detection device.
4. An underground nuclear power plant with a low-medium level waste disposal system according to claim 3, wherein: the waste treatment factory building is still including collecting waste treatment facility (21) airborne radioactive effluent's No. one gas collecting device (B1) and collection in low radioactive waste treatment tunnel (24), well radioactive effluent's No. two gas collecting devices (B2) in waste treatment tunnel (25) and spent fuel dry-type storage area (26), no. one gas collecting device (B1) and No. two gas collecting devices (B2) all link to have exhaust-gas treatment device, exhaust-gas treatment device is including gas-liquid separator (B3), active carbon guard bed (B4), one-level delay bed (B5) and the second grade delay bed (B6) that connect gradually, exhaust-gas treatment device's end is equipped with exhaust-gas detection device (B7), exhaust-gas treatment device's export with ventilation shaft (B8) at waste treatment factory building top communicate, gas-liquid separator (B3) with No. one waste liquid temporary storage tank (A1) intercommunication.
5. The underground nuclear power plant with low-medium level waste disposal system of claim 4, wherein: the waste treatment facility (21) is provided with a washroom, and the waste treatment plant is arranged in a plurality of layers and comprises a process treatment area, an auxiliary process area, a control area, a heating ventilation room and an electric instrument control plant.
6. A method of disposing of an underground nuclear power plant having a low-medium level waste disposal system of claim 5, wherein: the radioactive waste gas treatment device of the nuclear auxiliary factory building (114) is used for treating waste gas of the power generation area (1), the SRTF site waste discharge treatment facility (21) is used for collecting and treating radioactive waste water from the power generation area (1), the SRTF site waste discharge treatment facility (21), the low-level waste treatment tunnel (24), the medium-level waste treatment tunnel (25) and the spent fuel dry storage area (26), barreling and solidifying evaporation and concentration residual liquid, and the distilled liquid and the low-level filtrate are subjected to groove type monitoring and discharge through the discharge water groove (A12) after being qualified by sampling and detection; the SRTF site waste disposal facility (21) carries out gas-liquid separation and adsorption filtration on gas-borne radioactive effluents of the SRTF site waste disposal facility (21), a low-level waste disposal tunnel (24), a medium-level waste disposal tunnel (25) and a spent fuel dry storage area (26), and the gas-liquid-separated and adsorption filtration is discharged to the ventilation vertical shaft (B8) after being qualified by detection; the SRTF site waste disposal facility (21) is used for processing, sorting, solidifying and packaging a waste drying steel drum (A11) after waste liquid treatment and low-medium level solid waste from the power generation area (1), and respectively conveying the waste drying steel drum to the low-level waste disposal tunnel (24) and the medium-level waste disposal tunnel (25) through the waste disposal area traffic tunnel (23) for final disposal according to the activity of radioactive substances of the waste drum; the spent fuel dry storage area (26) temporarily stores spent fuel which decays and releases heat from the fuel factory (112) during the operation of the power generation area (1), and the spent fuel is transported to the ground through the waste transport tunnel (22) and the power generation area traffic tunnel (12) by a special transport container after the spent fuel dry storage area (26) is fully piled up.
7. The method of disposal of an underground nuclear power plant having a low-medium level waste disposal system of claim 6, wherein: after the waste liquid in the first waste liquid temporary storage tank (A1), the second waste liquid temporary storage tank (A2) and the waste liquid transferring container (A3) is sampled and detected, the radioactivity and the chemical salt content of the waste liquid are obtained, when the waste liquid is high in salt content and high in activity, the waste liquid passes through the first waste liquid treatment device, is filtered by the first filter (A4), is heated by the preheater (A5) and then enters the evaporator (A6), the distilled liquid is injected into the waste drying steel drum (A11) for solidification treatment, the distilled liquid is subjected to steam-water separation by the steam-water separator (A7), the steam re-enters the evaporator (A6), the distilled liquid enters the distilled liquid storage tank (A10) after passing through the cooler (A8) and the salt removal bed (A9), and the waste liquid which is qualified in sampling detection is led to the field waste water discharge system of the power generation area (1) through the discharge water tank (A12) to be discharged out of the field waste water discharge system; when the waste liquid is low in salt and activity, the waste liquid passes through the second waste liquid treatment device, is filtered by the second filter (A13), passes through the ion exchange column (A14), is properly discharged to the discharge water tank (A12) through sampling detection, and is discharged out of the field waste water discharge system of the power generation area (1).
8. The method of disposal of an underground nuclear power plant having a low-medium level waste disposal system of claim 6, wherein: waste gas that gas collecting device (B1) and No. two gas collecting devices (B2) were collected is passed through behind gas-liquid separator (B3), the waste liquid that separates gets into No. one waste liquid temporary storage tank (A1), waste gas passes through active carbon protection bed (B4), one-level delay bed (B5) and second grade delay bed (B6) adsorb and filter, warp exhaust gas detection device (B7) discharge to ventilation shaft (B8) after detecting qualified, detect unqualified waste gas and carry out cyclic treatment.
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| CN110400649B (en) * | 2019-07-29 | 2021-09-24 | 中国核电工程有限公司 | Method and structure for disposing radioactive waste cavern with low reclaimed water level |
| CN110534221B (en) * | 2019-09-06 | 2024-04-12 | 长江勘测规划设计研究有限责任公司 | Mobile waste liquid treatment system of underground nuclear power station |
| CN111933321B (en) * | 2020-07-17 | 2024-06-07 | 中核核电运行管理有限公司 | Heavy water pile radioactive waste liquid discharge loop system and method |
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