CN103985426A - Disposal method for radioactive wet solid wastes of nuclear facilities - Google Patents
Disposal method for radioactive wet solid wastes of nuclear facilities Download PDFInfo
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- CN103985426A CN103985426A CN201410206686.XA CN201410206686A CN103985426A CN 103985426 A CN103985426 A CN 103985426A CN 201410206686 A CN201410206686 A CN 201410206686A CN 103985426 A CN103985426 A CN 103985426A
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Abstract
The invention discloses a disposal method for radioactive wet solid wastes of nuclear facilities. The method comprises the followings: 1), radioactive wet solid wastes to be disposed directly fill an HDPE-HIC container; (2), dehydration is performed on the HDPE-HIC container filled with the wet solid waste until the content of free water in the container meets the requirements of sub-surface disposal of low and middle level radioactive wet solid wastes; (3), the HDPE-HIC container is capped after dehydration, and conveyed to a waste working-storage facility for working-storage treatment. Compared with the prior art, the disposal method for the radioactive wet solid wastes of the nuclear facilities can reduce waste volume through that the solid wastes directly fill the HDPE-HIC container for dehydration, is not only conducive to minimizing of final wastes, but also improves the waste disposal safety.
Description
Technical field
The invention belongs to nuclear facilities radioactive waste process field, more particularly, the present invention relates to the disposal route of the wet solid waste of low, the middle radioactivity of a kind of nuclear facilities.
Background technology
The various nuclear facilities run durations that comprise nuclear power station, capital produces the wet solid waste of radioactivity such as useless filter core, spent resin, radioactive nuclide in these wet solid waste exists with a kind of unstable form, may be to environment disperse or migration in environment once be exposed to, so that cause the pollution to environment, therefore must process.Along with the fast development of global nuclear power in recent years, at the wet solid waste of the radioactivity of building nuclear power station and produce at fortune nuclear power station, be on the increase, therefore, realize the focal point that waste minimization has become current Solid Waste Treatment technology.
Existing nuclear facilities all adopts comparatively ripe cement solidification technology to process wet solid waste such as useless filter core, spent resins.Refer to Fig. 1, the technological process of typical cement solidification technology is: 1) for the processing of useless filter core, first adopt special-purpose useless filter element replacing device that the useless filter element replacing in water filter is got off; Metal drum (each metal drum is only put a useless filter core) transport and put into the useless filter element replacing device filter core that will give up subsequently, then by the raceway of metal drum bottom, metal drum is sent to grouting station, the filter core that gives up carried out to cementation process and fix; Then by raceway, metal drum is sent to relative stations and carries out that capping, surface dose rate detect and maintenance is processed; Finally being sent to the temporary facility of refuse keeps in; 2), for spent resin is processed, first by spent resin storage tank, collect the spent resin producing except salt bed; The spent resin of collecting is after temporary a period of time, by gravity flow or be sent to spent resin through hydraulic ejector and stock groove and carry out metering volume or weight, load in mixture by a certain percentage in metal drum with dry blend, adjuvant subsequently, raceway by metal drum bottom is sent to mixing plant by metal drum and stirs again, realizes the curing processing of spent resin; Then, by raceway, metal drum is sent to relative stations and carries out that capping, surface dose rate detect and maintenance is processed, be finally sent to the temporary facility of refuse temporary.
But at least there is following defect in existing cement solidification technology:
1) the refuse volume after cement solidification processing is 1.8～2.5 with the ratio of initial refuse volume, that is to say, cement solidification technology increases the volume of final refuse, is unfavorable for waste minimization;
2) cement solidification technology is capacity increasing technique, and it has not only improved the final disposal cost of radioactive waste bag, and can cause the waste of disposal site land resource;
3) cement solidification technology institute adopting process equipment is more, technological operation is comparatively complicated, thereby the cost that has improved system operation, maintenance drops into;
4) when radioactive spent resin and dry blend, adjuvant etc. stir in metal drum, paddle is inserting, is proposing in metal drum and whipping process, radioactive waste in bucket all may splash to outside bucket, thereby cause process equipment pickup and occur the focus that radioactivity is higher, bring irradiation risk to operations staff's execute-in-place;
5) cement solidification technology does not have online sampler in spent resin treatment process, thereby can not obtain the source item data of spent resin in pail for used dressings, is unfavorable for the management of the links such as temporary, the transportation of pail for used dressings and disposal.
Summary of the invention
The object of the invention is to: provide a kind of wet solid waste treatment method of nuclear facilities radioactivity that can be conducive to final waste minimization, to reduce the treatment and disposal cost of nuclear facilities radioactive waste.
In order to realize foregoing invention object, the invention provides the wet solid waste treatment method of a kind of nuclear facilities radioactivity, it comprises the following steps:
1) the wet solid waste of pending radioactivity is directly loaded in HDPE-HIC container;
2) to being housed, the HDPE-HIC container of wet solid waste dewaters, until the free water content in container meets the shallow ground disposal requirement of low middle Intermediate Level Radioactive solid waste;
3) by the HDPE-HIC closing flaps after dehydration, and be transported to the temporary facility of refuse and keep in processing.
As a kind of improvement of the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, the wet solid waste of described pending radioactivity comprises useless filter core and spent resin, and described spent resin comprises acticarbon.
A kind of improvement as the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, described useless filter core is loading before HDPE-HIC container, need to first change and transport, concrete steps are: utilize useless filter element replacing device that the useless filter core that does not meet request for utilization in water filter is taken out, and pack in shielding transfer container; By transport carriage, the shielding transfer container that useless filter core is housed is transported to HIC filling station; Utilize crane shielding transfer container is sling and delivered to directly over the HDPE-HIC container that is positioned at concrete shield container; Open the lid of shielding transfer container bottom, make useless filter core fall into HDPE-HIC container; Confirm that useless filter core falls into after HDPE-HIC container, crane hangs back shielding transfer container on transport carriage again; Repeat abovementioned steps, until fill useless filter core in HDPE-HIC container.
A kind of improvement as the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, the useless filter core that described useless filter element replacing device more swaps out is before packing shielding transfer container into, need to first carry out surface dose rate detection: if useless filter core dose rate does not surpass limit value, put it in shielding transfer container; If useless filter core dose rate has surpassed limit value, put it in temporary container and store decay, until useless filter core dose rate, be reduced to and be no more than after limit value, the useless filter element replacing device of the recycling filter core that will give up takes out, and packs into shield in transfer container and transports.
As a kind of improvement of the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, described each shielding transfer container only fills a useless filter core.
A kind of improvement as the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, described spent resin is loading before HDPE-HIC container, need to first collect, keep in and carry, concrete steps are: utilize spent resin storage tank to collect and keep in the spent resin except salt bed discharge; When the spent resin in spent resin storage tank meets emission request, spent resin will be from spent resin storage tank by deadweight or spray and enter spent resin intake pipeline by hydraulic jeting device, then enter through spent resin delivery line the spent resin filling device being connected with delivery line end; Spent resin is drained into the HDPE-HIC container that is arranged in concrete shield container by filling device, admission space is monitored by the level switch or the liquid level gauge that are configured on filling device.
A kind of improvement as the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, the upstream delivery line of described spent resin filling device is provided with the online sampler of spent resin, online sampler carries out online sampling to spent resin and detects, and its sampling frequency and sample volume regulate according to actual needs.
A kind of improvement as the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, described spent resin filling device is arranged on HDPE-HIC container top, and be closely connected with HDPE-HIC vessel port, to prevent that the outer of radioactivity resin from spattering or being with active gasoloid excessive.
A kind of improvement as the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, described step 2) in, first utilize dehydration plant to carry out several dewatering cycle to being filled with the HDPE-HIC container of wet solid waste, then the water of deviating from is for the last time entered to dehydration and detect groove, by the measurement liquid volume detecting in groove of dewatering, judge whether the free water yield in HDPE-HIC container is less than 1%: if liquid volume is less than 1% of refuse volume in HDPE-HIC container, stop dewatering and carrying out subsequent step; Otherwise, repeat dehydration, until detecting liquid volume in groove, dehydration is less than 1% of refuse volume in HDPE-HIC container.
As a kind of improvement of the wet solid waste treatment method of nuclear facilities radioactivity of the present invention, described step 1) in HDPE-HIC container be to be positioned in the concrete shield container with shielding action; In described step 3) in, first utilize capping apparatus to carry out capping to the HDPE-HIC container after dewatering; Then with crane and gripping apparatus, the HDPE-HIC container after capping is hung out from concrete shield container, directly handling to temporary facility is kept in processing, or lift after shielded coffin, then by shielded coffin, be transported to the temporary facility of refuse and keep in processing.
Compared with prior art, the wet solid waste treatment method of nuclear facilities radioactivity of the present invention is by directly loading wet solid waste into HDPE-HIC container the mode of dewatering, reduce the volume of refuse, be not only conducive to final waste minimization, and improved the security that refuse is processed.
Accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, the wet solid waste treatment method of nuclear facilities radioactivity of the present invention is elaborated.
Fig. 1 is the process chart of the wet solid waste cement solidification technology of existing nuclear facilities radioactivity.
Fig. 2 is the process chart of the wet solid waste treatment method of nuclear facilities radioactivity of the present invention.
Embodiment
In order to make goal of the invention of the present invention, technical scheme and useful technique effect thereof more clear, below in conjunction with the drawings and specific embodiments, the present invention is further elaborated.Should be understood that, the embodiment of describing in this instructions is only used to explain the present invention, is not intended to limit the present invention.
HDPE-HIC container (High Density Polyethylene High Integrity Container, the high whole container of high density polyethylene) be a kind of by high density polyethylene (High Density Polyethylene, HDPE) container that material rotational moulding processes, it has compared with performances such as high chemical stability, thermal stability, resistance to biodegradation and resistance to irradiation, and expected service life is 300 years.HDPE-HIC container can directly be packed the wet refuse of low, middle radioactivity, can not cause the increase-volume of treated waste.Therefore, the present invention proposes a kind of HDPE-HIC of usining container as the waste treatment method of the wet solid waste packing container of low, middle radioactivity, the steps include: first to utilize support equipment to change/collect the wet solid waste of radioactivity such as useless filter core, spent resin, and it is directly loaded in HDPE-HIC container; Then to being housed, the HDPE-HIC container of wet solid waste dewaters, until free water content meets the shallow ground disposal requirement of low middle Intermediate Level Radioactive solid waste in container; Finally the HDPE-HIC Container transfering after dehydration to the temporary facility of refuse is kept in to processing.
The wet solid waste treatment method of nuclear facilities radioactivity of the present invention, according to dissimilar useless filter core disposal route and spent resin (the comprising activated charcoal) disposal route of being divided into of processing wet solid waste, is elaborated to the two respectively below with reference to the process chart shown in Fig. 2.
The step of the useless filter core disposal route of the present invention is:
1) useless filter element replacing: utilize useless filter element replacing device that the useless filter core that does not meet request for utilization in water filter is taken out, and the surface dose rate of the useless filter core of detection: if useless filter core dose rate does not surpass limit value, put it in shielding transfer container, and each container only fills a useless filter core; If useless filter core dose rate has surpassed limit value, put it into temporary container and store decay, until useless filter core dose rate, be reduced to and be no more than after limit value, the useless filter element replacing device of the recycling filter core that will give up takes out, and packs into and shields in transfer container; Adopting the temporary technology of useless filter core is in order to reduce the radioactive level of useless filter core, to prevent that HDPE-HIC container cumulative absorbed dose from surpassing limit value requirement; In addition, while packing the useless filter core after temporary into shielding transfer container, can from temporary container, choose the filter core of suitable dimension, by the filter core of reasonably combined different size, improve the loadings of useless filter core in HDPE-HIC container;
2) useless filter core transhipment: the shielding transfer container that useless filter core is housed is transported to HIC filling station by transport carriage;
3) useless filter core is packed into HDPE-HIC container: utilize crane shielding transfer container is sling and delivered to directly over the HDPE-HIC container that is positioned at concrete shield container; Open the lid of shielding transfer container bottom, make useless filter core fall into HDPE-HIC container; Confirm that useless filter core falls into after HDPE-HIC container, crane hangs back shielding transfer container on transport carriage again; Repeat abovementioned steps, until fill useless filter core in HDPE-HIC container;
4) HDPE-HIC container dehydration: utilize dehydration plant to carry out several dewatering cycle (each dewatering cycle is a few hours loading the HDPE-HIC container of completely useless filter core, after suspending a period of time, carry out again a few hours dehydration, reciprocal according to this), when dehydration completes substantially, the water of deviating from from HDPE-HIC container is for the last time entered to dehydration and detect groove, by measurement, dewater and detect liquid volume in groove and judge in HDPE-HIC container, whether free water amount is less than 1%: if liquid volume be less than refuse volume in HDPE-HIC container 1% time, stop dewatering; Otherwise, repeat dehydration, until detecting liquid volume in groove, dehydration is less than 1% of refuse volume in HDPE-HIC container;
5) HDPE-HIC closing flaps is temporary: the HDPE-HIC container after utilizing capping apparatus to dehydration carries out capping; Can the HDPE-HIC container after capping be hung out from concrete shield container with crane and supporting gripping apparatus, pack shielded coffin into and be transported to the temporary facility of refuse and keep in processings, also can the direct handling of HDPE-HIC container after capping extremely be kept in to facility with crane and supporting gripping apparatus and keep in processing.
The step of spent resin disposal route of the present invention is:
1) spent resin is collected: utilize spent resin storage tank to collect nuclear facilities except the spent resin in salt bed; When being discharged to spent resin in spent resin storage tank by waterpower punching and meeting emission request, spent resin will be by conducting oneself with dignity or being sprayed and entered spent resin intake pipeline by hydraulic jeting device from spent resin storage tank, and spent resin can obtain certain flow rate while discharging and avoid spent resin blocking pipe and valve in pipeline is carried;
2) spent resin is carried: spent resin enters the spent resin filling device being connected with delivery line end by spent resin delivery line, and is sampled by the online sampler being arranged on the delivery line of spent resin filling device upstream; The sampling frequency of the online sampler of spent resin and sample volume can be set according to actual needs;
3) spent resin is packed into HDPE-HIC container: the spent resin after sampling is drained into the HDPE-HIC container that is arranged in concrete shield container by filling device, admission space is monitored by the level switch or the liquid level gauge that are configured on filling device; Because spent resin filling device is arranged on HDPE-HIC container top, and be closely connected with HDPE-HIC vessel port, therefore can prevent that the outer of radioactivity resin from spattering or being with active gasoloid excessive;
4) HDPE-HIC container dehydration: the spent resin in HDPE-HIC container reaches after predetermined, (each dewatering cycle is a few hours to utilize dehydration plant to carry out several dewatering cycle to HDPE-HIC container, after suspending a period of time, carry out again a few hours dehydration, reciprocal according to this), when dehydration completes substantially, the water of deviating from from HDPE-HIC container is for the last time entered to dehydration and detect groove, by measurement, dewater and detect liquid volume in groove and judge in HDPE-HIC container, whether free water amount is less than 1%: if liquid volume be less than refuse volume in HDPE-HIC container 1% time, stop dehydration, otherwise, repeat dehydration, until detecting liquid volume in groove, dehydration is less than 1% of refuse volume in HDPE-HIC container,
5) HDPE-HIC closing flaps is temporary: the HDPE-HIC container after utilizing capping apparatus to dehydration carries out capping; Can utilize crane and special-purpose gripping apparatus that the HDPE-HIC container after capping is hung out from concrete shield container, then pack temporary processing of carrying out that shielded coffin is transported to the temporary facility of refuse into, also can utilize crane and special-purpose gripping apparatus that the direct handling of HDPE-HIC container after capping to temporary facility is kept in to processing.
Known by above description, the wet solid waste treatment method of nuclear facilities radioactivity of the present invention at least has following beneficial effect:
First, adopt HDPE-HIC container directly to load the wet solid waste of radioactivity, compare with traditional cement solidification capacity increasing technique, more being conducive to realize radioactive waste minimizes, it is consistent that the refuse not only requiring with national legislation is processed developing direction, and can be because long-pending the reducing and reduce refuse bag and dispose expense of refuse inclusion has good economy;
The second, equipment needed thereby is less, and is modularized equipment, and structure is also comparatively simple, thus the manufacture of equipment and installation period shorter, the cost of later stage operation and maintenance and difficulty are all lower;
The 3rd, waste delivery, transhipment are all carried out in pipeline or airtight container, and refuse is closely connected with HDPE-HIC vessel port when filling HDPE-HIC container, so can effectively prevent that radiomaterial is excessive; Meanwhile, HDPE-HIC container is placed in concrete shield container, is conducive to reduce operating personnel's radioactive dose; In HDPE-HIC container processing procedure, device therefor all passes through remote control operation; Above measure has all improved the security that refuse is processed;
The 4th, on spent resin delivery line, dispose online sampler, therefore can obtain in time nuclide composition and the level of activity of radiomaterial in refuse bag, can formulate in advance rational technical scheme refuse bag is carried out to safety, economic keeping in, transport and dispose, be conducive to improve the efficiency that radioactive waste is processed.
Visible, compared with prior art, the wet solid waste treatment method of nuclear facilities radioactivity of the present invention is used in combination by HDPE-HIC container and other support equipments, is conducive to minimizing of final refuse, and has improved the security that refuse is processed.
The announcement of book and instruction according to the above description, those skilled in the art in the invention can also carry out suitable change and modification to above-mentioned embodiment.Therefore, the present invention is not limited to embodiment disclosed and described above, to modifications and changes more of the present invention, also should fall in the protection domain of claim of the present invention.In addition,, although used some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the present invention.
Claims (10)
1. the wet solid waste treatment method of nuclear facilities radioactivity, is characterized in that comprising the following steps:
1) the wet solid waste of pending radioactivity is directly loaded in HDPE-HIC container;
2) to being housed, the HDPE-HIC container of wet solid waste dewaters, until the free water content in container meets the shallow ground disposal requirement of low middle Intermediate Level Radioactive solid waste;
3) by the HDPE-HIC closing flaps after dehydration, and be transported to the temporary facility of refuse and keep in processing.
2. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 1, is characterized in that: the wet solid waste of described pending radioactivity comprises useless filter core and spent resin.
3. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 2, it is characterized in that: described useless filter core is loading before HDPE-HIC container, need to first change and transport, concrete steps are: utilize useless filter element replacing device that the useless filter core that does not meet request for utilization in water filter is taken out, and pack in shielding transfer container; By transport carriage, the shielding transfer container that useless filter core is housed is transported to HIC filling station; Utilize crane shielding transfer container is sling and delivered to directly over the HDPE-HIC container that is positioned at concrete shield container; Open the lid of shielding transfer container bottom, make useless filter core fall into HDPE-HIC container; Confirm that useless filter core falls into after HDPE-HIC container, crane hangs back shielding transfer container on transport carriage again; Repeat abovementioned steps, until fill useless filter core in HDPE-HIC container.
4. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 3, it is characterized in that: the useless filter core that described useless filter element replacing device more swaps out, before packing shielding transfer container into, need first to carry out surface dose rate detection: if useless filter core dose rate does not surpass limit value, put it in shielding transfer container; If useless filter core dose rate has surpassed limit value, put it in temporary container and store decay, until useless filter core dose rate, be reduced to and be no more than after limit value, the useless filter element replacing device of the recycling filter core that will give up takes out, and packs into shield in transfer container and transports.
5. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 4, is characterized in that: described each shielding transfer container only fills a useless filter core.
6. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 2, it is characterized in that: described spent resin is loading before HDPE-HIC container, need to first collect, keep in and carry, concrete steps are: utilize spent resin storage tank to collect and keep in the spent resin except salt bed discharge; When the spent resin in spent resin storage tank meets emission request, spent resin will be from spent resin storage tank by deadweight or spray and enter spent resin intake pipeline by hydraulic jeting device, then enter through spent resin delivery line the spent resin filling device being connected with delivery line end; Spent resin is drained into the HDPE-HIC container that is arranged in concrete shield container by filling device, admission space is monitored by the level switch or the liquid level gauge that are configured on filling device.
7. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 6, it is characterized in that: the upstream delivery line of described spent resin filling device is provided with the online sampler of spent resin, online sampler carries out online sampling to spent resin and detects, and its sampling frequency and sample volume regulate according to actual needs.
8. the wet solid waste treatment method of nuclear facilities radioactivity according to claim 6, is characterized in that: described spent resin filling device is arranged on HDPE-HIC container top, and is closely connected with HDPE-HIC vessel port.
9. according to the wet solid waste treatment method of the nuclear facilities radioactivity described in any one in claim 1 to 8, it is characterized in that: described step 2), first utilize dehydration plant to carry out several dewatering cycle to being filled with the HDPE-HIC container of wet solid waste, then the water of deviating from is for the last time entered to dehydration and detect groove, by the measurement liquid volume detecting in groove of dewatering, judge whether the free water yield in HDPE-HIC container is less than 1%: if liquid volume is less than 1% of refuse volume in HDPE-HIC container, stop dewatering and carrying out subsequent step; Otherwise, repeat dehydration, until detecting liquid volume in groove, dehydration is less than 1% of refuse volume in HDPE-HIC container.
10. according to the wet solid waste treatment method of the nuclear facilities radioactivity described in any one in claim 1 to 8, it is characterized in that: the HDPE-HIC container described step 1) is to be positioned in the concrete shield container with shielding action; In described step 3) in, first utilize capping apparatus to carry out capping to the HDPE-HIC container after dewatering; Then with crane and gripping apparatus, the HDPE-HIC container after capping is hung out from concrete shield container, directly handling to temporary facility is kept in processing, or lift after shielded coffin, then by shielded coffin, be transported to the temporary facility of refuse and keep in processing.
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| CN104575647A (en) * | 2015-01-04 | 2015-04-29 | 上海核工程研究设计院 | Radioactive waste resin shielding transfer method and device |
| CN104575647B (en) * | 2015-01-04 | 2017-01-18 | 上海核工程研究设计院 | Radioactive waste resin shielding transfer method and device |
| CN105280262A (en) * | 2015-09-17 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant waste package dehydration device and method |
| CN105280262B (en) * | 2015-09-17 | 2018-11-09 | 中广核工程有限公司 | A kind of nuclear power plant's waste packet dehydration device and method |
| CN105355252A (en) * | 2015-10-09 | 2016-02-24 | 中广核工程有限公司 | Method and system for treating low-medium radioactive level filter core of filter in nuclear power station |
| CN105355252B (en) * | 2015-10-09 | 2017-09-01 | 中广核工程有限公司 | Nuclear power station low middle zoom level radioactivity filter element processing method and system |
| CN106448782A (en) * | 2016-12-13 | 2017-02-22 | 中广核工程有限公司 | Waste filter cartridge transfer container of nuclear power plant |
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| CN108682469A (en) * | 2018-05-22 | 2018-10-19 | 中国核电工程有限公司 | A kind of modular Radwastes treatment center arrangement method |
| CN111158037A (en) * | 2020-01-02 | 2020-05-15 | 中广核工程有限公司 | Nuclear facility solid waste package radioactivity evaluation method and system |
| CN111158037B (en) * | 2020-01-02 | 2022-03-15 | 中广核工程有限公司 | Nuclear facility solid waste package radioactivity evaluation method and system |
| CN112599276A (en) * | 2020-12-09 | 2021-04-02 | 中广核研究院有限公司 | Nuclear power plant radioactive waste filter element carrying device |
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