CN108766604B - Calculation method for identifying irradiation dose by K3 type in-situ box irradiation resistance in nuclear reactor - Google Patents
Calculation method for identifying irradiation dose by K3 type in-situ box irradiation resistance in nuclear reactor Download PDFInfo
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- CN108766604B CN108766604B CN201810377999.XA CN201810377999A CN108766604B CN 108766604 B CN108766604 B CN 108766604B CN 201810377999 A CN201810377999 A CN 201810377999A CN 108766604 B CN108766604 B CN 108766604B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
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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
- 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
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention belongs to the technical field of nuclear radiation monitoring, and relates to a calculation method for identifying irradiation dose by K3 type on-site box irradiation resistance in a nuclear reactor. The calculation method fully considers the irradiation dose and the irradiation time under different accident conditions, and respectively calculates the serious accident condition and the design benchmark accident condition. By using the calculation method for identifying the irradiation dose of the K3 type in-situ box in the nuclear power reactor, the technical blank can be filled up to verify whether the in-situ box can meet the safety function under different accident conditions under the identification requirement of third-generation nuclear power.
Description
Technical Field
The invention belongs to the technical field of nuclear radiation monitoring, and relates to a calculation method for identifying irradiation dose by K3 type on-site box irradiation resistance in a nuclear reactor.
Background
The third generation nuclear power provides new requirements for equipment identification. For the instrument control ground box, the largest change is that the 1E/K3 class ground box has the requirement of irradiation resistance identification, which is not required in the past identification projects. As the irradiation resistance identification of the 1E/K3 type in-situ box almost belongs to the technical blank in the past nuclear power project, the research on the irradiation resistance requirement of the 1E/K3 type in-situ box in the third-generation nuclear power has great significance.
Disclosure of Invention
The invention aims to provide a calculation method for identifying irradiation dose by irradiation resistance of K3 type in-situ boxes in nuclear power reactor type, so as to fill up the technical blank and verify whether the type of in-situ boxes can meet the safety function under different accident conditions under the identification requirement of third-generation nuclear power.
In order to achieve the purpose, in a basic embodiment, the invention provides a calculation method for identifying the irradiation dose of a K3 type local box irradiation-resistant in-situ reactor type, wherein the calculation method fully considers the irradiation dose and the irradiation time under different accident conditions and respectively calculates the serious accident condition and the design benchmark accident condition.
According to the invention, the irradiation doses of different radiation areas are respectively calculated according to two working conditions of a design benchmark accident and a serious accident, so that the irradiation doses under different working conditions are fully considered, on one hand, the identification test can cover the two accident working conditions of the nuclear power station, and on the other hand, the identification requirement is not excessively increased, so that the identification activity fails.
According to the calculation method, through analyzing K3 equipment which needs to execute safety functions under the condition of a nuclear power station reference accident and a serious accident and related control links thereof, related 1E-level K3 instrument control place, platform, screen, box and cabinet are screened, and radiation dosage which should be endured in identification of the 1E-level K3 instrument control place, platform, screen, box and cabinet of the third-generation nuclear power station is calculated by combining radiation partition.
The invention defines the irradiation dose which the 1E-grade K3 instrument control site, platform, screen, box and cabinet of the third-generation nuclear power station should endure in the identification process, and fills the gap in the third-generation nuclear power technology.
In a preferred embodiment, the invention provides a calculation method for identifying irradiation dose of K3 type in-situ box irradiation resistance in a nuclear reactor type, wherein the calculation method classifies components, and verification calculation is respectively carried out according to 100Gy, 30KGy and 70KGy in the calculation process according to different irradiation resistance capacities of different components.
The invention fully considers the radiation resistance of different components, combines the arrangement areas of instrument control ground plates, boxes and cabinets applied by different types of components, optimally classifies all the components needing radiation resistance identification, and improves the success rate of the identification activity to the greatest extent.
In a preferred embodiment, the invention provides a calculation method for identifying the irradiation dose of a K3 type in-situ box irradiation-resistant nuclear reactor, wherein the calculation of the serious accident condition sequentially comprises the following steps:
(1) cleaning 1E/K3 type equipment which needs to execute safety function under serious accident, combing control links of the equipment, and marking room number and radiation area for local boxes on the control links respectively;
(2) classifying the marked rooms, and inquiring the accumulated dose of each area of the nuclear island plant and the maximum accumulated dose data of the marked rooms after serious accidents;
(3) cleaning all the types of the components contained in the on-site box, and determining the irradiation dose of the irradiation-resistant appraisal according to the cleaning type result.
In a more preferred embodiment, the invention provides a method for calculating the irradiation-resistant identification irradiation dose of K3 type in-situ boxes in a nuclear reactor type, wherein in the step (3), all main components contained in all the type in-situ boxes determined by cleaning are terminal rows, and the irradiation-resistant identification irradiation dose of the terminal rows is determined according to a past irradiation-resistant groping test, so that the irradiation-resistant identification irradiation dose of the type in-situ boxes is determined.
In a preferred embodiment, the invention provides a calculation method for identifying the irradiation dose by the irradiation resistance of a K3 in-situ box in a nuclear reactor type, wherein the calculation of the design reference accident condition sequentially comprises the following steps:
(1) for a 1E/K3 type on-site box which deals with the non-serious accident condition outside the containment, from the perspective of conservative verification, design reference accident condition data is adopted for verification;
(2) inquiring the accumulated dose of each area of the nuclear island plant and the maximum accumulated dose data of the nuclear island plant rooms after the design benchmark accident
(3) Cleaning all the types of the components contained in the on-site box, and determining the irradiation dose of the irradiation-resistant appraisal according to the cleaning type result.
In a more preferred embodiment, the invention provides a method for calculating the irradiation dose of the K3 type in-situ box irradiation-resistant qualification in the nuclear reactor, wherein in the step (3), all the determined main components contained in all the type in-situ boxes are cleaned and are electronic components, the in-situ boxes for all the electronic components are further cleaned, the room number and the radiation area are marked, and the irradiation dose of the irradiation-resistant qualification is determined according to the marked maximum radiation area.
In a more preferred embodiment, the invention provides a calculation method for identifying the irradiation dose of a K3 type in-situ box in a nuclear reactor, wherein in the step (3), all main components contained in the determined in-situ box are cleaned and determined as mechanical components, and the irradiation dose of the in-situ box is determined according to a previous irradiation resistance empirical test.
The method has the beneficial effects that by utilizing the calculation method for identifying the irradiation dose of the K3 type in-situ box in the nuclear power reactor type, the technical blank can be filled, and whether the type of in-situ box can meet the safety function under different accident working conditions under the identification requirement of third-generation nuclear power can be verified.
The calculation method can meet the identification requirements of all 1E/K3 type on-site boxes under the currently known working conditions, and the calculation result is feasible through the verification test and passes the verification test.
Detailed Description
The calculation method for identifying the irradiation dose of the K3 type on-site box in the nuclear power reactor fully considers the irradiation dose and the irradiation time under different accident conditions, and respectively calculates the serious accident condition and the design benchmark accident condition. The calculation method classifies the components, and verification calculation is respectively carried out according to 100Gy, 30KGy and 70KGy in the calculation process according to the difference of the radiation resistance of different components.
(1) Severe accident condition
It is first necessary to clean the 1E/K3 type devices that need to perform safety functions in case of serious accidents and to comb the control links of these devices, marking the room number and the radiation area respectively for the local boxes used in these control links.
And secondly, classifying the marked rooms, and inquiring the accumulated dose of each area of the nuclear island plant and the maximum accumulated dose of the marked rooms after a serious accident. According to the query result, the following steps are carried out: the accumulated dose of the 1E/K3 type on-site box in the normal service life (10 years) is 8.76KGy, and the maximum accumulated dose of the marking room after a serious accident is 61KGy, which totals 69.76 KGy.
And thirdly, cleaning all components contained in the on-site box. After cleaning, all the main components contained in the in-situ box are terminal blocks, and according to the previous radiation resistance and touch test, the terminal blocks are preliminarily considered to have the capability of resisting 69.76 KGy.
Therefore, for the 1E/K3 type on-site box which only contains the terminal row and needs to deal with the serious accident outside the containment, the irradiation resistant identification dose value is 69.76 KGy.
(2) Design reference accident regime
Firstly, verifying the 1E/K3 type on-site box which deals with the non-serious accident condition outside the containment by adopting design reference accident condition data from the viewpoint of conservative verification.
Secondly, inquiring the accumulated dose of each area of the nuclear island plant and the maximum accumulated dose data of the nuclear island plant rooms after the design benchmark accident. According to the query result, the following steps are carried out: the accumulated dosage of the 1E/K3 type local box in the normal service life (10 years) is 8.76KGy, and the maximum accumulated dosage (calculated by taking the maximum time of 1 year) of the nuclear island factory building room after the design benchmark accident is 21KGy, which totals 29.76 KGy.
And thirdly, cleaning all components contained in the on-site box. After cleaning, the components contained in the on-site box are various and very complex. The components can be classified according to their main components: one is an electronic component, and the other is a mechanical component. According to the previous radiation-resistant and touchdown test, the electronic components have very low radiation resistance, so that all in-place boxes applied to the electronic components are cleaned, and the room number and the radiation area are marked. After marking, the area of such in-situ box placement was the most heavily dosed orange II zone, with a cumulative dose of 87.6Gy over the lifetime (10 years). And for mechanical components, the capability of resisting 29.76KGy is preliminarily judged according to the conventional radiation-resistant and groping test.
By comprehensively considering the two working conditions, the invention calculates the irradiation dose of the K3 type on-site box irradiation-resistant identification in the three-generation nuclear reactor type, and the formed result is as follows:
(1) for a 1E/K3 type on-site box which only contains a terminal row and needs to deal with the serious accident outside the containment, the irradiation-resistant identification dose value is 69.76 KGy;
(2) for mechanical components contained in a 1E/K3 on-site box which does not need to deal with serious accidents outside the containment, the irradiation-resistant identification dose value is 29.76 KGy;
(3) for electronic components contained in a 1E/K3 in-situ box which does not need to deal with serious accidents outside the containment, the irradiation resistant identification dose value is 87.6 Gy.
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 above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or 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. The calculation method for identifying the irradiation dose of the K3 type in-situ box irradiation resistance in the nuclear reactor type is characterized by comprising the following steps: the calculation method fully considers the irradiation dose and the irradiation time under different accident working conditions, and respectively calculates the serious accident working condition and the design reference accident working condition;
the calculation of the severe accident condition sequentially comprises the following steps:
(1) cleaning 1E/K3 type equipment which needs to execute safety function under serious accident, combing control links of the equipment, and marking room number and radiation area for local boxes on the control links respectively;
(2) classifying the marked rooms, and inquiring the accumulated dose of each area of the nuclear island plant and the maximum accumulated dose data of the marked rooms after serious accidents;
(3) cleaning all component types contained in the on-site box, and determining the irradiation dose of irradiation resistance identification according to the cleaning type result;
the calculation of the design reference accident condition sequentially comprises the following steps:
(a) for a 1E/K3 type on-site box which deals with the working condition of a non-serious accident outside a containment, from the perspective of conservative verification, design reference accident working condition data is adopted for verification;
(b) inquiring the accumulated dose of each area of the nuclear island plant and the maximum accumulated dose data of the nuclear island plant rooms after the design benchmark accident;
(c) cleaning all the types of the components contained in the on-site box, and determining the irradiation dose of the irradiation-resistant appraisal according to the cleaning type result.
2. The computing method according to claim 1, characterized in that: the calculation method classifies the components, and verification calculation is respectively carried out according to 100Gy, 30KGy and 70KGy in the calculation process according to the difference of the radiation resistance of different components.
3. The computing method according to claim 2, characterized in that: in the step (3), all the main components contained in the in-situ box are cleaned and determined as the terminal strip, and the irradiation-resistant identification irradiation dose of the terminal strip is determined according to the previous irradiation-resistant touchdown test, so that the irradiation-resistant identification irradiation dose of the in-situ box is determined.
4. The computing method according to claim 1, characterized in that: in the step (c), the main components contained in all the determined in-situ boxes are cleaned and are electronic components, the in-situ boxes applied by all the electronic components are further cleaned, the room number and the radiation area are marked, and the irradiation resistance and the irradiation dose are determined according to the marked maximum radiation area.
5. The computing method according to claim 1, characterized in that: in the step (c), all the main components contained in the cleaning and determining type of on-site boxes are mechanical components, and the irradiation resistance identification irradiation dose of the on-site boxes is determined according to the previous irradiation resistance groping test.
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| CN104296803A (en) * | 2014-09-18 | 2015-01-21 | 中国核电工程有限公司 | Digital nuclear facility environmental radiation monitoring system |
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| CN1748219A (en) * | 2003-02-09 | 2006-03-15 | 阿拉里医疗设备有限公司 | Medication management and event logger and analysis system |
| CN104296803A (en) * | 2014-09-18 | 2015-01-21 | 中国核电工程有限公司 | Digital nuclear facility environmental radiation monitoring system |
Non-Patent Citations (2)
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| CPR1000严重事故仪表鉴定要求的对比分析及应用;唐华雄等;《核科学与工程》;20121231;第1.1-1.2、2.2小节 * |
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