CN106297927A - A kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident - Google Patents
A kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident Download PDFInfo
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- CN106297927A CN106297927A CN201510240064.3A CN201510240064A CN106297927A CN 106297927 A CN106297927 A CN 106297927A CN 201510240064 A CN201510240064 A CN 201510240064A CN 106297927 A CN106297927 A CN 106297927A
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The present invention provides a kind of and is applicable to the method that PWR nuclear power plant Spent Fuel Pool major accident processes, including: a, the water level depth obtaining Spent Fuel Pool and the Factory Building radiopharmaceutical agent dose rate that Spent Fuel Pool is corresponding；B, when water level depth less than preset first threshold or Factory Building radiopharmaceutical agent dose rate more than preset Second Threshold time, then perform a Spent Fuel Pool accident treatment program；C, after accident treatment program has performed, the further detection water level depth of Spent Fuel Pool, pond temperature and Factory Building radiopharmaceutical agent dose rate；Water level depth, pond temperature and Factory Building radiopharmaceutical agent dose rate that d, judgement detect the most all meet predetermined condition；E is if it is, accident treatment terminates；If it is not, then re-execute an accident treatment program, return step c.Implementing the present invention, it is possible to when processing spent nuclear fuel in nuclear power plant pond and major accident occurring, quickly feature and accident analysis result according to Spent Fuel Pool carry out accident mitigation.
Description
Technical field
The present invention relates to the technical field of nuclear power plant's accident treatment, particularly relate to a kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident.
Background technology
Spent Fuel Pool is as the storage facilities of spent nuclear fuel in nuclear power plant, it can persistently release decay heat, under specific circumstances it may happen that major accidents such as fuel assembly fusings, therefore the safety of Spent Fuel Pool causes the extensive concern of domestic and international nuclear power industry, it is necessary the safety of Spent Fuel Pool is analyzed, especially it is Spent Fuel Pool generation major accident, it is possible to the accident treatment of Spent Fuel Pool is formed a series for the treatment of mechanism.
At present, only exist reactor core and have an accident the diagnostic flow chart and directive/guide processed, but when processing spent nuclear fuel in nuclear power plant pond and major accident occurring, lack the method that quickly can carry out accident mitigation according to feature and the accident analysis result of Spent Fuel Pool.
Summary of the invention
Embodiment of the present invention technical problem to be solved is, there is provided a kind of and be applicable to the method that PWR nuclear power plant Spent Fuel Pool major accident processes, can be when processing spent nuclear fuel in nuclear power plant pond and major accident occurring, quickly feature and accident analysis result according to Spent Fuel Pool carry out accident mitigation.
In order to solve above-mentioned technical problem, embodiments providing a kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident, described method includes:
A, the water level depth obtaining Spent Fuel Pool and the Factory Building radiopharmaceutical agent dose rate that described Spent Fuel Pool is corresponding；
B, when the described Spent Fuel Pool got water level depth less than the first threshold preset or described in Factory Building radiopharmaceutical agent dose rate corresponding to the Spent Fuel Pool that gets more than the Second Threshold preset time, then Spent Fuel Pool accident treatment starts, and performs a Spent Fuel Pool accident treatment program；
C, after described Spent Fuel Pool accident treatment program has performed, the further detection water level depth of described Spent Fuel Pool, pond temperature and Factory Building radiopharmaceutical agent dose rate；
The water level depth of Spent Fuel Pool, pond temperature and the Factory Building radiopharmaceutical agent dose rate that detect described in d, judgement the most all meet predetermined condition；
E is if it is, Spent Fuel Pool accident treatment terminates；
F, if it is not, then re-execute the most described Spent Fuel Pool accident treatment program, returns step c.
Wherein, described Spent Fuel Pool accident treatment program includes the water filling program sequentially performed, cooling recovery routine and reduces fission product release procedure.
Wherein, the concrete steps of described water filling program include:
When the water level depth described Spent Fuel Pool being detected is less than three threshold value preset, then enters SAG-1, perform the operation to described Spent Fuel Pool water filling；
When the water level depth of described Spent Fuel Pool being detected more than described default three threshold value, then terminate the operation to described Spent Fuel Pool water filling.
Wherein, the concrete steps of described cooling recovery routine include:
When the pond temperature described Spent Fuel Pool being detected is more than four threshold value preset, then enter SAG-2, perform the operation recovering that described Spent Fuel Pool is cooled down；
When the pond temperature of described Spent Fuel Pool being detected less than described default four threshold value, then terminate the operation that described Spent Fuel Pool is cooled down.
Wherein, the concrete steps of described minimizing fission product release procedure include:
When the Factory Building radiopharmaceutical agent dose rate described Spent Fuel Pool being detected is more than five threshold value preset, then enter SAG-3, perform to reduce the operation of fission product in the described Spent Fuel Pool of release, reduce described Factory Building radiopharmaceutical agent dose rate；
When the Factory Building radiopharmaceutical agent dose rate of described Spent Fuel Pool being detected less than described default five threshold value, then terminate reducing and discharge the operation of fission product in described Spent Fuel Pool, determine that described Factory Building radiopharmaceutical agent dose rate is normal.
Wherein, described Spent Fuel Pool accident treatment program can be by identifying that available path and equipment operate accordingly in Factory Building corresponding to described Spent Fuel Pool.
Wherein, described equipment includes fixing equipment and mobile device.
Wherein, described first threshold is 12m；Described Second Threshold is 10 mGy/h.
Wherein, described 3rd threshold value is 15.5m.
Wherein, described 4th threshold value is 65 DEG C.
Implement the embodiment of the present invention, have the advantages that
1, the present invention can be when processing spent nuclear fuel in nuclear power plant pond and major accident occurring, and quickly feature and accident analysis result according to Spent Fuel Pool carry out accident mitigation；
2, the present invention can simultaneously with the processing method of reactor core generation major accident with the use of, be reduced as far as the release of fission product；
3, the present invention can effectively use mobile device to carry out accident treatment (such as mobile pump, portable power source, flexible pipe etc.) in complex environment.
Accompanying drawing explanation
In order to be illustrated more clearly that the embodiment of the present invention or technical scheme of the prior art, the accompanying drawing used required in embodiment or description of the prior art will be briefly described below, apparently, accompanying drawing in describing below is only some embodiments of the present invention, for those of ordinary skill in the art, on the premise of not paying creative work, the accompanying drawing obtaining other according to these accompanying drawings still falls within scope of the invention.
The flow chart being applicable to the method that PWR nuclear power plant Spent Fuel Pool major accident processes that Fig. 1 provides for the embodiment of the present invention；
The flow chart being applicable to the method application scenarios that PWR nuclear power plant Spent Fuel Pool major accident processes that Fig. 2 provides for the embodiment of the present invention.
Detailed description of the invention
For making the object, technical solutions and advantages of the present invention clearer, below in conjunction with accompanying drawing, the present invention is described in further detail.
Inventor finds, when occurring the whole audience loss of power accident and power supply cannot recover for a long time under nuclear power plant is in refuelling outage operating mode, although nuclear power plant can success shutdown, but it is likely to be due to lack long term thermal trap, reactor core deteriorates faster, eventually deteriorate into major accident, therefore should first start the processing routine to reactor core.Once find that Spent Fuel Pool is likely to be due to lose refrigerating function, and fuel assembly decay heat cannot be taken out of so that the water in Spent Fuel Pool seethes with excitement and evaporates, and directive/guide water level is gradually lowered, therefore before Spent Fuel Pool accident develops into major accident, it is also desirable to enter corresponding processing routine.To this end, inventors herein propose a kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident, can use with processing method during reactor core generation major accident simultaneously, be reduced as far as the release of fission product.
As it is shown in figure 1, a kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident proposed for inventor, described method includes:
Step S101, the water level depth obtaining Spent Fuel Pool and the Factory Building radiopharmaceutical agent dose rate that described Spent Fuel Pool is corresponding；
Detailed process is, by obtaining the water level depth of Spent Fuel Pool and the Factory Building radiopharmaceutical agent dose rate that Spent Fuel Pool is corresponding, differentiates whether Spent Fuel Pool occurs major accident.
Step S102, when the described Spent Fuel Pool got water level depth less than the first threshold preset or described in Factory Building radiopharmaceutical agent dose rate corresponding to the Spent Fuel Pool that gets more than the Second Threshold preset time, then Spent Fuel Pool accident treatment starts, and performs a Spent Fuel Pool accident treatment program；
Detailed process is, when the Factory Building radiopharmaceutical agent dose rate that the water level depth of Spent Fuel Pool is corresponding with Spent Fuel Pool less than the first threshold preset is set up more than any of which of the Second Threshold preset, just it is considered as Spent Fuel Pool generation major accident, then starts Spent Fuel Pool accident treatment and perform Spent Fuel Pool accident treatment program (simultaneously can using with processing method during reactor core generation major accident).Wherein, first threshold can be set to 12m, and Second Threshold can be set to 10 mGy/h.
It is understood that owing to 12m is embodiment of the present invention center Power Plant Fuel assembly elevation of top water level, therefore the set point of first threshold can carry out a certain amount of setting of floating on the basis of fuel assembly top (such as 12m).
Should be noted that, before starting Spent Fuel Pool accident treatment and performing Spent Fuel Pool accident treatment program, it is considered as in the case of Spent Fuel Pool is leak free, it is first turned on the passage (such as having already turned on then holding valve state constant) that reloads, if then there is major accident in reactor pit and Spent Fuel Pool simultaneously, calculated curve in the case of should connecting with Spent Fuel Pool according to reactor pit, performs the step in Spent Fuel Pool accident treatment program.
In embodiments of the present invention, Spent Fuel Pool accident treatment program includes the water filling program sequentially performed, cooling recovery routine and reduces fission product release procedure.Wherein,
(1) concrete steps of water filling program include: when water level depth Spent Fuel Pool being detected is less than three threshold value preset, then enters SAG-1, perform the operation to Spent Fuel Pool water filling；When water level depth Spent Fuel Pool being detected is more than three threshold value preset, then terminate the operation to Spent Fuel Pool water filling.Wherein, the 3rd threshold value is the biological shielding liquid level that nuclear power plant sets, and biological shielding liquid level in embodiments of the present invention is 15.5m.
It should be noted that, owing to reactor pit and Spent Fuel Pool occur major accident simultaneously, be considered as the calculated curve in the case of reactor pit connects with Spent Fuel Pool and choose water injection rate.
It is understood that due in the embodiment of the present invention biological shielding liquid level of nuclear power plant be 15.5m, when water level higher than 15.5m time, water has preferable shielding action；When water level is less than 15.5m, neighbouring radiation dose comparatively fast can increase with the reduction of liquid level, therefore can be according to practical situation, it is considered on the basis of biological shielding liquid level (such as 15.5m), deviation ± 25% sets the 3rd threshold value.
(2) concrete steps of cooling recovery routine include: when pond temperature Spent Fuel Pool being detected is more than four threshold value preset, then enter SAG-2, perform to recover the operation to Spent Fuel Pool cooling；When pond temperature Spent Fuel Pool being detected is less than four threshold value preset, then terminate the operation to Spent Fuel Pool cooling.Wherein, the 4th threshold value is 65 DEG C.
It is understandable that, owing to when the pond temperature of Spent Fuel Pool is when higher than its temperature 20% under normal circumstances, there is liquid level warning function, and prompting have the risk of boiling, therefore can be according to practical situation, it is considered on the basis of 65 DEG C, deviation ± 10% sets the 4th threshold value.
(3) concrete steps reducing fission product release procedure include: when Factory Building radiopharmaceutical agent dose rate Spent Fuel Pool being detected is more than five threshold value preset, then enter SAG-3, perform to reduce the operation of fission product in release Spent Fuel Pool, reduce Factory Building radiopharmaceutical agent dose rate；When Factory Building radiopharmaceutical agent dose rate Spent Fuel Pool being detected is less than five threshold value preset, then terminates reducing the operation of fission product in release Spent Fuel Pool, determine that Factory Building radiopharmaceutical agent dose rate is normal.Wherein, the 5th threshold value is the upper limit of the radioactive dosage that nuclear power plant is arranged according to the built environment of Spent Fuel Pool Factory Building, and the upper limit generally arranged can be considered place and meet an urgent need level.
In embodiments of the present invention, Spent Fuel Pool accident treatment program can be by identifying that available path and equipment operate accordingly in Factory Building corresponding to Spent Fuel Pool.As in water filling program, identify that available water filling path and equipment carry out water flood operations；In cooling recovery routine, identify that available transfer path and heat exchanger carry out cooling down operation；In reducing fission product release procedure, identify the path that fission product is discharging, take device spray point of release or close the operation of hull closure stopping fission product release.
Wherein, equipment includes fixing equipment and mobile device；Fixing equipment includes pump, power supply, valve, pipeline etc., and mobile device includes mobile pump, portable power source, flexible pipe etc..
In one embodiment, when Spent Fuel Pool incident processing procedure finding, fixing equipment is unavailable, or current fixing equipment cannot complete incidence graph major accident process, then in Spent Fuel Pool accident treatment program circuit, it is reserved with interface, directly invoke mobile device and carry out major accident process, thus realize the effective purpose using mobile device that major accident is processed in complex environment.
Step S103, after described Spent Fuel Pool accident treatment program has performed, the further detection water level depth of described Spent Fuel Pool, pond temperature and Factory Building radiopharmaceutical agent dose rate；
Detailed process is, after detection Spent Fuel Pool accident treatment program has performed, and the water level depth of Spent Fuel Pool, pond temperature and Factory Building radiopharmaceutical agent dose rate, differentiate whether the accident of current Spent Fuel Pool is eased.
The water level depth of Spent Fuel Pool, pond temperature and the Factory Building radiopharmaceutical agent dose rate that detect described in step S104, judgement the most all meet predetermined condition；If it is, perform next step S105, if it is not, then redirect execution step S106；
Detailed process is, predetermined condition can set according to water level depth, pond temperature and Factory Building radiopharmaceutical agent dose rate.In one embodiment, predetermined condition includes: the water level depth of (I) Spent Fuel Pool is more than 15.5m, and keeps stable；(II) pond temperature is less than 65 DEG C, and stablizes or declining；(III) Factory Building radiopharmaceutical agent dose rate is met an urgent need level less than place, and stable or declining.
When water level depth, pond temperature and Factory Building radiopharmaceutical agent dose rate meet predetermined condition simultaneously, then Spent Fuel Pool accident treatment terminates；Otherwise, continue executing with Spent Fuel Pool accident treatment program, till water level depth, pond temperature and Factory Building radiopharmaceutical agent dose rate all meet predetermined condition.
Step S105, Spent Fuel Pool accident treatment terminate；
Step S106, re-execute the most described Spent Fuel Pool accident treatment program, return step S3.
As in figure 2 it is shown, a kind of application scenarios being applicable to the method that PWR nuclear power plant Spent Fuel Pool major accident processes in the embodiment of the present invention is further illustrated:
Monitoring nuclear power plant important parameter when step 201, execution Emergency operation guidance, including Spent Fuel Pool water level and fuel Factory Building dosage.When monitoring Spent Fuel Pool water level depth less than 12m or Factory Building close rate more than 10mGy/h, then Spent Fuel Pool accident treatment starts, and enters Spent Fuel Pool major accident processing routine；
Step 202, first determine whether that Spent Fuel Pool water level depth is whether more than 15.5m；The most then perform step 203；If it is not, then enter SAG-1, i.e. after Spent Fuel Pool water filling, then perform step 203；
Step 203, judge that the pond temperature of Spent Fuel Pool is whether less than 65 DEG C；The most then perform step 204；If it is not, then enter SAG-2, after i.e. recovering Spent Fuel Pool cooling, then perform step 204；
Step 204, judge whether whether on-the-spot emission levels meet an urgent need level, i.e. Factory Building radiopharmaceutical agent dose rate less than the upper limit arranged less than place；The most then perform step 205；If it is not, then enter SAG-3, after i.e. reducing fission product release, perform step 205 again；
Step 205, finally enter major accident exit criteria and judge, carry out the judgement of following parameter: first Spent Fuel Pool water level is higher than 15.5m；Secondly Spent Fuel Pool temperature is less than 65 DEG C；Again, on-the-spot release is met an urgent need level less than place.If above-mentioned condition all meets, then it is assumed that parameters is the most up to standard, major accident processes and terminates；If cannot all meet, then return step 202, re-start process and diagnosis.
Implement the embodiment of the present invention, have the advantages that
1, the present invention can be when processing spent nuclear fuel in nuclear power plant pond and major accident occurring, and quickly feature and accident analysis result according to Spent Fuel Pool carry out accident mitigation；
2, the present invention can simultaneously with the processing method of reactor core generation major accident with the use of, be reduced as far as the release of fission product；
3, the present invention can effectively use mobile device to carry out accident treatment (such as mobile pump, portable power source, flexible pipe etc.) in complex environment.
Above disclosed it is only one preferred embodiment of the present invention, certainly can not limit the interest field of the present invention, the equivalent variations therefore made according to the claims in the present invention with this, still belong to the scope that the present invention is contained.
Claims (10)
1. one kind is applicable to the method that PWR nuclear power plant Spent Fuel Pool major accident processes, it is characterised in that described method includes:
A, the water level depth obtaining Spent Fuel Pool and the Factory Building radiopharmaceutical agent dose rate that described Spent Fuel Pool is corresponding；
B, when the described Spent Fuel Pool got water level depth less than the first threshold preset or described in Factory Building radiopharmaceutical agent dose rate corresponding to the Spent Fuel Pool that gets more than the Second Threshold preset time, then Spent Fuel Pool accident treatment starts, and performs a Spent Fuel Pool accident treatment program；
C, after described Spent Fuel Pool accident treatment program has performed, the further detection water level depth of described Spent Fuel Pool, pond temperature and Factory Building radiopharmaceutical agent dose rate；
The water level depth of Spent Fuel Pool, pond temperature and the Factory Building radiopharmaceutical agent dose rate that detect described in d, judgement the most all meet predetermined condition；
E is if it is, Spent Fuel Pool accident treatment terminates；
F, if it is not, then re-execute the most described Spent Fuel Pool accident treatment program, returns step c.
2. the method for claim 1, it is characterised in that described Spent Fuel Pool accident treatment program includes the water filling program sequentially performed, cooling recovery routine and reduces fission product release procedure.
3. method as claimed in claim 2, it is characterised in that the concrete steps of described water filling program include:
When the water level depth described Spent Fuel Pool being detected is less than three threshold value preset, then enters SAG-1, perform the operation to described Spent Fuel Pool water filling；
When the water level depth of described Spent Fuel Pool being detected more than described default three threshold value, then terminate the operation to described Spent Fuel Pool water filling.
4. method as claimed in claim 2, it is characterised in that the concrete steps of described cooling recovery routine include:
When the pond temperature described Spent Fuel Pool being detected is more than four threshold value preset, then enter SAG-2, perform the operation recovering that described Spent Fuel Pool is cooled down；
When the pond temperature of described Spent Fuel Pool being detected less than described default four threshold value, then terminate the operation that described Spent Fuel Pool is cooled down.
5. method as claimed in claim 2, it is characterised in that the concrete steps of described minimizing fission product release procedure include:
When the Factory Building radiopharmaceutical agent dose rate described Spent Fuel Pool being detected is more than five threshold value preset, then enter SAG-3, perform to reduce the operation of fission product in the described Spent Fuel Pool of release, reduce described Factory Building radiopharmaceutical agent dose rate；
When the Factory Building radiopharmaceutical agent dose rate of described Spent Fuel Pool being detected less than described default five threshold value, then terminate reducing and discharge the operation of fission product in described Spent Fuel Pool, determine that described Factory Building radiopharmaceutical agent dose rate is normal.
6. as described in claim 2 method, it is characterised in that described Spent Fuel Pool accident treatment program available path and equipment can operate in the Factory Building corresponding by identifying described Spent Fuel Pool accordingly.
7. method as claimed in claim 6, it is characterised in that described equipment includes fixing equipment and mobile device.
8. the method for claim 1, it is characterised in that described first threshold is 12m；Described Second Threshold is 10 mGy/h.
9. method as claimed in claim 3, it is characterised in that described 3rd threshold value is 15.5m.
10. method as claimed in claim 4, it is characterised in that described 4th threshold value is 65 DEG C.
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| CN112652415A (en) * | 2020-12-01 | 2021-04-13 | 中国辐射防护研究院 | Post-processing plant emergency state grading determination method based on characteristic parameter analysis |
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| CN113421670A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Nuclear power plant accident regulation quantitative analysis method and system |
| CN113421670B (en) * | 2021-06-18 | 2022-05-13 | 中国核动力研究设计院 | Nuclear power plant accident regulation quantitative analysis method and system |
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Effective date of registration: 20170818 Address after: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Applicant after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Applicant after: Lingao Nuclear Power Co., Ltd. Applicant after: China General Nuclear Power Corporation Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant before: China General Nuclear Power Corporation Applicant before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. |
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Effective date of registration: 20181126 Address after: 518000 Futian District, Shenzhen, Guangdong, Futian District, 15 steps (1502-1504, 1506) of Shenzhen science and technology building. Applicant after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Applicant after: Lingao Nuclear Power Co., Ltd. Applicant after: China General Nuclear Power Corporation Applicant after: China Nuclear Power Engineering Co., Ltd. Address before: 518031 Futian District, Shenzhen, Guangdong, Futian District, 15 steps (1502-1504, 1506) of Shenzhen science and technology building. Applicant before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Applicant before: Lingao Nuclear Power Co., Ltd. Applicant before: China General Nuclear Power Corporation |
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Application publication date: 20170104 |
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