CN112652415B - Post-processing plant emergency state grading determination method based on characteristic parameter analysis - Google Patents
Post-processing plant emergency state grading determination method based on characteristic parameter analysis Download PDFInfo
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- CN112652415B CN112652415B CN202011381577.3A CN202011381577A CN112652415B CN 112652415 B CN112652415 B CN 112652415B CN 202011381577 A CN202011381577 A CN 202011381577A CN 112652415 B CN112652415 B CN 112652415B
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- 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
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- 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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Abstract
The invention relates to a method for determining the emergency state of a post-processing plant based on characteristic parameter analysis in a grading manner, which comprises the following steps: step 1, describing main facilities of a post-treatment plant; step 2, analyzing typical accidents of main facilities of the post-processing plant; step 3, determining characteristic parameters related to typical accidents of main facilities of the post-processing plant, and analyzing the characteristic parameters; and 4, determining the emergency state classification of the post-treatment plant. The method for determining the emergency state of the post-processing plant in the grading manner provided by the invention relates the potential accident type and severity in the post-processing plant with various characteristic parameters and indications thereof in the accident process, thereby making an emergency action level which is consistent with the actual situation.
Description
Technical Field
The invention belongs to the technical field of nuclear industry, and relates to a method for determining emergency states of a post-processing plant in a grading manner based on characteristic parameter analysis.
Background
The nuclear fuel circulation facility divides the emergency state into four levels according to the severity of the radiation consequences of possible events and accidents and the emergency response action to be taken, and the emergency state is emergency standby, factory emergency, field emergency and off-site emergency. Each emergency condition has its basic characteristics and corresponding qualitative or quantitative criteria.
The emergency state of the nuclear fuel circulation facility may include two stages (emergency standby, plant emergency), may include three stages (emergency standby, plant emergency, and site emergency), and may include even four stages (emergency standby, plant emergency, site emergency, and off-site emergency), depending on the type, characteristics, and the like of the nuclear fuel circulation facility. The level of emergency situations that can occur in a nuclear fuel recycling installation can therefore be determined analytically by the type of nuclear accident that has occurred and its installation consequences etc. For most nuclear fuel circulation facilities in China, off-site emergency is generally not considered, but facilities with higher potential risks may need to be implemented. It must be ensured that the established emergency grading system can cover all emergency situations that may occur in its facility.
For a nuclear fuel cycle plant, the classification criteria for the four emergency states are not completely quantitative criteria, and even quantitative criteria, only radiation consequences are generally considered. For possible emergency situations, a link to the radiation consequences needs to be established by the characteristic parameters.
Characteristic parameters of typical accident scenarios of the post-processing plant and the relation between the typical accident scenarios and the emergency state are not all clear up to now.
Disclosure of Invention
Aiming at the defects in the prior art, the invention provides a method for determining the emergency state of the post-processing plant in a grading manner based on characteristic parameter analysis, so as to establish the relation between the typical accident situation of the post-processing plant and the emergency state and grasp the type and severity of the potential accident in the post-processing plant.
In order to achieve the purpose, the invention adopts the technical scheme that:
the method for determining the emergency state of the post-processing plant in a grading manner based on characteristic parameter analysis comprises the following steps:
step 1, describing main facilities of a post-treatment plant;
step 2, analyzing typical accidents of main facilities of the post-processing plant;
step 3, determining characteristic parameters related to typical accidents of main facilities of the post-processing plant, and analyzing the characteristic parameters;
and 4, determining the emergency state classification of the post-processing plant.
Further, the main facilities of the post-treatment plant comprise a spent fuel receiving and storing facility, a post-treatment process facility and a high-level radioactive liquid waste treatment facility.
Further, typical accident scenarios of the spent fuel receiving and storing facility include a spent fuel storage pool cooling system failure, and an abnormal drop in water level.
Further, typical accidents of the post-treatment process facility include critical accidents, red oil explosion accidents, organic phase combustion accidents.
Further, typical accident scenarios of the high-level radioactive liquid waste treatment facility include a storage tank hydrogen explosion accident and a storage tank leakage accident.
Further, the characteristic parameters of the critical accident include critical control quality or control concentration, peripheral dose equivalent rate, gamma dose rate, and radioactive aerosol concentration; the characteristic parameters of the organic phase fire accident comprise solvent leakage, aerosol, temperature, light intensity, gamma dose rate and radioactive aerosol concentration; the characteristic parameters of the red oil explosion accident comprise liquid level in the evaporator, temperature, pressure, density, sump liquid level, radioactive aerosol concentration and environment gamma dose rate.
Further, the characteristic parameters of the hydrogen explosion accident of the storage tank comprise liquid level, temperature, pressure, density, hydrogen concentration, sump liquid level, gamma dose rate and radioactive aerosol concentration in the storage tank; the characteristic parameters of the storage tank leakage accident comprise liquid level of a liquid level sump in the storage tank, gamma dose rate, radioactive aerosol concentration and environment gamma dose rate.
Further, the characteristic parameters of the faults of the spent fuel storage pool cooling system comprise pool water temperature and gamma dose rate; the characteristic parameters of the abnormal reduction of the water level of the spent fuel storage pool comprise the liquid level of the pool, the temperature of the pool water and gamma dose rate.
Further, the specific method for determining the emergency state classification of the post-processing plant in the step 4 is as follows:
(1) When two parameters of critical control quality or control concentration exceed the normal process operation limit value, the risk of a potential critical accident is indicated, and emergency standby is carried out at the moment;
(2) When the equivalent rate of peripheral dose monitored by a critical accident alarm instrument and the gamma dose rate monitored by a fixed gamma monitor exceed a certain limit value for a certain time, entering a factory for emergency;
(3) When the gamma dose rate monitored by a fixed gamma monitor and the radioactive aerosol concentration monitored by an iCAM aerosol continuous measurement instrument exceed a certain limit value for a certain time, entering a field area for emergency;
(4) When the gamma dose rate monitored by the fixed gamma monitor and the radioactive aerosol concentration monitored by the iCAM aerosol continuous measurement instrument exceed a higher limit value for a certain time, the system enters an off-site emergency.
The invention has the beneficial technical effects that: the method for determining the emergency state of the post-processing plant based on the characteristic parameter analysis quantifies the accident/event and the consequence thereof, can master the potential accident type and the severity degree in the post-processing plant through the process, and can work out the emergency action level which is consistent with the reality through being associated with various characteristic parameters and indications thereof in the accident process.
Drawings
FIG. 1 is a step diagram of a method for grading and determining an emergency state of an aftertreatment plant based on characteristic parameter analysis according to the present invention.
Detailed Description
The following describes embodiments of the present invention in further detail with reference to the accompanying drawings.
As shown in fig. 1, the present invention provides a method for hierarchically determining an emergency state of an aftertreatment plant based on characteristic parameter analysis, the method comprising the steps of:
step 1, describing main facilities of a post-treatment plant; the main facilities of the post-treatment plant comprise a spent fuel receiving and storing facility, a post-treatment process facility and a high-level radioactive waste liquid treatment facility.
Step 2, analyzing typical accidents of main facilities of the post-processing plant; typical accident scenarios of the spent fuel receiving and storing facility include a spent fuel storage pool cooling system failure, and an abnormal drop in water level. Typical accidents of the post-treatment process facility include critical accidents, red oil explosion accidents, and organic phase combustion accidents. Typical accident situations of the high-level radioactive liquid waste treatment facility comprise a hydrogen explosion accident of a storage tank and a leakage accident of the storage tank.
And 3, determining characteristic parameters related to typical accidents of main facilities of the post-processing plant, and analyzing the characteristic parameters. The characteristic parameters of the emergency status grading corresponding to a typical accident are shown in table 1.
TABLE 1
And 4, determining the emergency state classification of the post-treatment plant. Taking the case of dealing with the critical accident of the main process facility later, the specific determination method is as follows:
(1) When two parameters of critical control quality or control concentration exceed the normal process operation limit value, the risk of a potential critical accident is indicated, and emergency standby can be carried out at the moment;
(2) When the equivalent rate of the peripheral dose monitored by a critical accident alarm instrument and the gamma dose rate monitored by a fixed gamma monitor exceed a certain limit value for a certain time, entering a factory building for emergency;
(3) When the gamma dose rate monitored by a fixed gamma monitor and the radioactive aerosol concentration monitored by an iCAM aerosol continuous measurement instrument exceed a certain limit value for a certain time, entering a field area for emergency;
(4) When the gamma dose rate monitored by the fixed gamma monitor and the radioactive aerosol concentration monitored by the iCAM aerosol continuous measuring instrument exceed a higher limit value for a certain time, the system enters an off-site emergency.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (5)
1. A grading determination method for an emergency state of a post-processing plant based on characteristic parameter analysis is characterized by comprising the following steps:
step 1, describing main facilities of a post-treatment plant; the main facilities of the post-treatment plant comprise a spent fuel receiving and storing facility, a post-treatment process facility and a high-level radioactive waste liquid treatment facility;
step 2, analyzing typical accidents of main facilities of the post-processing plant; typical accidents of the post-treatment process facility comprise critical accidents, red oil explosion accidents and organic phase fire accidents;
step 3, determining characteristic parameters related to typical accidents of main facilities of the post-processing plant, and analyzing the characteristic parameters; the characteristic parameters of the critical accident comprise critical control quality or control concentration, peripheral dose equivalent rate, gamma dose rate and radioactive aerosol concentration; the characteristic parameters of the organic phase fire accident comprise solvent leakage, aerosol, temperature, light intensity, gamma dose rate and radioactive aerosol concentration; the characteristic parameters of the red oil explosion accident comprise liquid level in an evaporator, temperature, pressure, density, sump liquid level, radioactive aerosol concentration and environment gamma dose rate;
step 4, determining the emergency state classification of the post-processing plant; the method for grading the critical accident emergency state of the post-treatment process facility comprises the following steps: (1) When two parameters of critical control quality or control concentration exceed the normal process operation limit value, the risk of a potential critical accident is indicated, and emergency standby is carried out at the moment;
(2) When the equivalent rate of peripheral dose monitored by a critical accident alarm instrument and the gamma dose rate monitored by a fixed gamma monitor exceed a certain limit value for a certain time, entering a factory for emergency;
(3) When the gamma dose rate monitored by a fixed gamma monitor and the radioactive aerosol concentration monitored by an iCAM aerosol continuous measurement instrument exceed a certain limit value for a certain time, entering a field area for emergency;
(4) When the gamma dose rate monitored by the fixed gamma monitor and the radioactive aerosol concentration monitored by the iCAM aerosol continuous measurement instrument exceed a higher limit value for a certain time, the system enters an off-site emergency.
2. The method for grading an emergency state of an aftertreatment plant based on characteristic parameter analysis according to claim 1, wherein typical accident scenarios of the spent fuel receiving and storing facility include a spent fuel storage pool cooling system failure, and an abnormal drop in the spent fuel storage pool water level.
3. The method for hierarchically determining the emergency state of the post-processing plant based on the characteristic parameter analysis as claimed in claim 1, wherein typical accident scenarios of the high level wastewater treatment facility include a storage tank hydrogen explosion accident and a storage tank leakage accident.
4. A method for grading determination of emergency status of post-processing plant based on characteristic parameter analysis according to claim 3, wherein the characteristic parameters of hydrogen explosion accident of the storage tank include liquid level in the storage tank, temperature, pressure, density, hydrogen concentration, sump liquid level, gamma dose rate, radioactive aerosol concentration; the characteristic parameters of the storage tank leakage accident comprise the liquid level in the storage tank, the liquid level of a water collecting pit, the gamma dose rate, the radioactive aerosol concentration and the environment gamma dose rate.
5. The grading determination method for the emergency state of the aftertreatment plant based on the characteristic parameter analysis according to claim 2, wherein the characteristic parameters of the failure of the spent fuel storage pool cooling system comprise pool water temperature and gamma dose rate; the characteristic parameters of the abnormal reduction of the water level of the spent fuel storage pool comprise the liquid level of the pool, the temperature of the pool water and gamma dose rate.
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Citations (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4657727A (en) * | 1984-10-18 | 1987-04-14 | Michael E. Stern | Fission product barrier emergency event classification and response system |
| EP0631290A1 (en) * | 1993-06-24 | 1994-12-28 | Hitachi, Ltd. | Reprocessing plant and method of operating the same |
| CN101217064A (en) * | 2007-12-27 | 2008-07-09 | 大亚湾核电运营管理有限责任公司 | A fatal accident disposal for improved type gigawatt-level PWR nuclear power plant |
| CN102841600A (en) * | 2012-08-24 | 2012-12-26 | 中国核电工程有限公司 | Accidence safety analysis method for nuclear fuel reprocessing plant |
| CN103456136A (en) * | 2013-09-18 | 2013-12-18 | 戴会超 | Internet of Things framework type system for monitoring and early warning of major accident potential safety hazards of water conservancy and hydropower project |
| GB201409900D0 (en) * | 2014-06-04 | 2014-07-16 | Inst Jozef Stefan | Method and apparatus for assessing the state of a spent-fuel facility |
| CN104916339A (en) * | 2015-04-22 | 2015-09-16 | 中国核动力研究设计院 | Nuclear power plant emergency state diagnosis system and diagnosis method |
| CN106297927A (en) * | 2015-05-13 | 2017-01-04 | 中国广核集团有限公司 | A kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident |
| KR101752328B1 (en) * | 2016-11-30 | 2017-06-29 | 주식회사 미래와도전 | Educational and Training Simulation System for Emergency Response to Nuclear Accidents in Neighboring Countrie |
| CN108091409A (en) * | 2017-11-28 | 2018-05-29 | 大亚湾核电运营管理有限责任公司 | A kind of nuclear emergency set state diagnosis and the comprehensive estimation method of damage sequence |
| CN109387544A (en) * | 2018-09-03 | 2019-02-26 | 中国辐射防护研究院 | High activity liquid waste basin hydrogen gas mixture explosion source item evaluation method |
| CN109509567A (en) * | 2018-09-21 | 2019-03-22 | 中国辐射防护研究院 | The device and method of simulation post-processing organic phase combustion emissions aerosol release |
| CN109636112A (en) * | 2018-11-12 | 2019-04-16 | 中国辐射防护研究院 | A kind of accident sort method based on Environmental security incident response |
| CN110276473A (en) * | 2019-05-22 | 2019-09-24 | 中国辐射防护研究院 | A kind of optimization method and system of fcf emergency resources |
| CN110400042A (en) * | 2019-06-12 | 2019-11-01 | 中国辐射防护研究院 | Based on the determination method of the fcf emergency rating of Markov process |
| CN110598966A (en) * | 2019-03-28 | 2019-12-20 | 中国辐射防护研究院 | Method for grading equipment in post-processing facility based on risk guidance |
| CN111428326A (en) * | 2018-12-24 | 2020-07-17 | 核工业计算机应用研究所 | Nuclear emergency treatment measure generation method based on constraint satisfaction problem |
-
2020
- 2020-12-01 CN CN202011381577.3A patent/CN112652415B/en active Active
Patent Citations (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4657727A (en) * | 1984-10-18 | 1987-04-14 | Michael E. Stern | Fission product barrier emergency event classification and response system |
| EP0631290A1 (en) * | 1993-06-24 | 1994-12-28 | Hitachi, Ltd. | Reprocessing plant and method of operating the same |
| CN101217064A (en) * | 2007-12-27 | 2008-07-09 | 大亚湾核电运营管理有限责任公司 | A fatal accident disposal for improved type gigawatt-level PWR nuclear power plant |
| CN102841600A (en) * | 2012-08-24 | 2012-12-26 | 中国核电工程有限公司 | Accidence safety analysis method for nuclear fuel reprocessing plant |
| CN103456136A (en) * | 2013-09-18 | 2013-12-18 | 戴会超 | Internet of Things framework type system for monitoring and early warning of major accident potential safety hazards of water conservancy and hydropower project |
| GB201409900D0 (en) * | 2014-06-04 | 2014-07-16 | Inst Jozef Stefan | Method and apparatus for assessing the state of a spent-fuel facility |
| CN104916339A (en) * | 2015-04-22 | 2015-09-16 | 中国核动力研究设计院 | Nuclear power plant emergency state diagnosis system and diagnosis method |
| CN106297927A (en) * | 2015-05-13 | 2017-01-04 | 中国广核集团有限公司 | A kind of method being applicable to the process of PWR nuclear power plant Spent Fuel Pool major accident |
| KR101752328B1 (en) * | 2016-11-30 | 2017-06-29 | 주식회사 미래와도전 | Educational and Training Simulation System for Emergency Response to Nuclear Accidents in Neighboring Countrie |
| CN108091409A (en) * | 2017-11-28 | 2018-05-29 | 大亚湾核电运营管理有限责任公司 | A kind of nuclear emergency set state diagnosis and the comprehensive estimation method of damage sequence |
| CN109387544A (en) * | 2018-09-03 | 2019-02-26 | 中国辐射防护研究院 | High activity liquid waste basin hydrogen gas mixture explosion source item evaluation method |
| CN109509567A (en) * | 2018-09-21 | 2019-03-22 | 中国辐射防护研究院 | The device and method of simulation post-processing organic phase combustion emissions aerosol release |
| CN109636112A (en) * | 2018-11-12 | 2019-04-16 | 中国辐射防护研究院 | A kind of accident sort method based on Environmental security incident response |
| CN111428326A (en) * | 2018-12-24 | 2020-07-17 | 核工业计算机应用研究所 | Nuclear emergency treatment measure generation method based on constraint satisfaction problem |
| CN110598966A (en) * | 2019-03-28 | 2019-12-20 | 中国辐射防护研究院 | Method for grading equipment in post-processing facility based on risk guidance |
| CN110276473A (en) * | 2019-05-22 | 2019-09-24 | 中国辐射防护研究院 | A kind of optimization method and system of fcf emergency resources |
| CN110400042A (en) * | 2019-06-12 | 2019-11-01 | 中国辐射防护研究院 | Based on the determination method of the fcf emergency rating of Markov process |
Non-Patent Citations (4)
| Title |
|---|
| 乏燃料后处理厂高放废液和废有机溶剂处理系统典型安全问题分析;宋凤丽 等;《核科学与工程》;20150630;第35卷(第2期);第320-327页 * |
| 乏燃料后处理设施应急行动水平制订方法的探讨;黄树明 等;《中国科技成果》;20180627(第7期);第34-36页，第41页 * |
| 铀转化设施应急行动水平的制定方法;吴静 等;《核动力工程》;20160630;第37卷;第111-114页 * |
| 风险评价分级法在核燃料后处理厂事故分析中的应用研究;李锐柔;《中国优秀博硕士学位论文全文数据库(硕士)工程科技Ⅱ辑》;20190115(第1期);第C040-12页 * |
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