CN110287454B - Method for acquiring leakage position and crack size in leakage accident - Google Patents
Method for acquiring leakage position and crack size in leakage accident Download PDFInfo
- Publication number
- CN110287454B CN110287454B CN201910431646.8A CN201910431646A CN110287454B CN 110287454 B CN110287454 B CN 110287454B CN 201910431646 A CN201910431646 A CN 201910431646A CN 110287454 B CN110287454 B CN 110287454B
- Authority
- CN
- China
- Prior art keywords
- leakage
- accident
- size
- break
- monitoring data
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01D—MEASURING NOT SPECIALLY ADAPTED FOR A SPECIFIC VARIABLE; ARRANGEMENTS FOR MEASURING TWO OR MORE VARIABLES NOT COVERED IN A SINGLE OTHER SUBCLASS; TARIFF METERING APPARATUS; MEASURING OR TESTING NOT OTHERWISE PROVIDED FOR
- G01D21/00—Measuring or testing not otherwise provided for
- G01D21/02—Measuring two or more variables by means not covered by a single other subclass
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06F—ELECTRIC DIGITAL DATA PROCESSING
- G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
- G06F17/10—Complex mathematical operations
- G06F17/18—Complex mathematical operations for evaluating statistical data, e.g. average values, frequency distributions, probability functions, regression analysis
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Physics & Mathematics (AREA)
- Data Mining & Analysis (AREA)
- Mathematical Physics (AREA)
- Pure & Applied Mathematics (AREA)
- Computational Mathematics (AREA)
- Theoretical Computer Science (AREA)
- Mathematical Optimization (AREA)
- Mathematical Analysis (AREA)
- Evolutionary Biology (AREA)
- Operations Research (AREA)
- Probability & Statistics with Applications (AREA)
- Bioinformatics & Computational Biology (AREA)
- Algebra (AREA)
- Life Sciences & Earth Sciences (AREA)
- Databases & Information Systems (AREA)
- Software Systems (AREA)
- General Engineering & Computer Science (AREA)
- Bioinformatics & Cheminformatics (AREA)
- Alarm Systems (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a method for acquiring a leakage position and a break in a leakage accidentThe size method includes the steps of firstly, UF in a factory building 6 Carrying out pre-dangerous analysis on the leakage accident to obtain possible leakage positions and break sizes, and then calculating to obtain all readings of the HF monitor under the possible accident situation, wherein the readings are used as a preset data matrix; after the accident is over, interpolation is carried out according to the position of the HF monitoring data in the preset data matrix, and the leakage position and the crack size are reversely pushed. The method provided by the invention can rapidly determine UF 6 And determining a leakage source item according to the leakage position and the size of the break in the leakage accident, so as to timely perform emergency response.
Description
Technical Field
The invention relates to the technical field of nuclear radiation monitoring, in particular to a method for acquiring a leakage position and a break size in a leakage accident.
Background
The main uranium compounds in the production of nuclear fuel recycling plants are: UF (UF) 6 、UO 2 F 2 、UO 2 、U 3 O 8 . The external irradiation radiation level of uranium compounds is low and stable, the internal irradiation radiation characteristics of the external irradiation radiation are main radiation hazard factors, and chemical hazards of uranium compounds are also considered, so that the internal irradiation and chemical hazards caused by inhalation are mainly considered in emergency actions.
Production line raw material UF 6 The container was filled with 30B at 2237Kg, with a uranium metal content of approximately 1500Kg. The solid, liquid and state coexisting three-phase point is 64.1 ℃ (0.15 MPa). When the UF6 temperature is below the triple pointThe material can sublimate from solid state to gas state, and the gas state can also sublimate to solid state; when the UF6 temperature is higher than the triple point, the liquid state can be gasified to the gas state, and the gas state is condensed to the liquid state. UF6 is particularly active in its chemical properties, except for its radiation properties. Under general conditions, UF 6 Not with O 2 、N 2 、CO 2 The F contained in the water can react with water and organic matters, and the F is more corrosive. UF (UF) 6 Landing on the skin can cause skin burn, irritate eyes and respiratory tract, cause bronchitis, asthma, and cause pulmonary edema by massive inhalation.
UF 6 Is very soluble in water to produce UO 2 F 2 And HF. UF (UF) 6 When the smoke leaks into the air, hydrofluoric acid droplets are formed by water in the air, and white smoke can be observed.
UF 6 Leakage accidents can lead to acute poisoning of personnel, overdose radiation, and environmental pollution. In the emergency preparation and response (request opinion manuscript) of the nuclear safety code HAD002/07-201X, the nuclear fuel cycle facility operation unit, UF 6 UF in conversion, uranium enrichment and uranium fuel element plants 6 The leakage event is used as a reference accident for emergency planning of nuclear fuel circulation facilities.
UF may be caused for the reasons in Table 1 6 Leakage accident:
table 1: UF (UF) 6 Possible cause of leakage accidents
To UF 6 The leakage accident is effectively prepared and responded in an emergency way, the determination of the leakage source item is the primary task, and the determination of the source item needs to take the leakage position and the break size as input conditions.
UF is currently carried out at home and abroad 6 The research of leakage accidents is basically focused on the aspect of accident consequences, namely the research of diffusion behavior after leakage; for UF 6 Research on the mechanism of leakage accidents has been carried out, and substantial progress has not been made; research on UF6 leakage source determination aspectsThere is no substantial progress in the research, and it is assumed that the leak position and the break size are used as input conditions for the source term calculation.
Disclosure of Invention
In view of the drawbacks of the prior art, an object of the present invention is to provide a method for obtaining the location of a leak and the size of a break in a leak accident, in UF 6 After the leakage accident occurs, the leakage position and the crack size can be rapidly determined so as to carry out emergency response.
In order to achieve the above purpose, the technical scheme adopted by the invention is as follows:
a method of obtaining a leak location and a breach size in a leak incident, the method comprising the steps of:
(1) To UF in factory building 6 Carrying out pre-danger analysis on the leakage accident;
(2) Obtaining possible leakage positions and break sizes based on the analysis in the step (1);
(3) Calculating all possible leakage positions and breach sizes;
(4) Obtaining all readings of the HF monitor under the situation of possible accidents, and taking the readings as a preset data matrix;
(5) And after the accident is ended, interpolation is carried out according to the position of the HF monitoring data in the preset data matrix, and the leakage position and the crack size are reversely pushed.
Further, in the step (5), the number of the HF monitoring data is plural, the leakage position and the break size obtained based on the single HF monitoring data by back-pushing are not unique, and the union set of the leakage position and the break size obtained by back-pushing each HF monitoring data is taken as the intersection set, so that the unique leakage position and the unique break size are determined.
The invention has the beneficial effects that: the invention can be applied to UF 6 After the leakage accident occurs, the leakage position and the opening size are timely and accurately determined so as to determine the leakage source item, timely and effectively perform emergency preparation and response, and ensure the safe operation of the nuclear fuel circulation facility.
Drawings
Fig. 1 is a schematic flow chart of a method for obtaining a leakage position and a breach size in a leakage accident according to the present invention.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
As shown in fig. 1, a method for obtaining a leakage position and a break size in a leakage accident includes:
first, UF in factory building 6 Carrying out pre-danger analysis on the leakage accident;
it is assumed that the results as in table 2 have been obtained from a pre-hazard analysis.
Table 2: results from prior hazard analysis
Wherein:
p is the possible leakage position;
a is the number of possible leak locations;
d is the size of the break;
b. c and e are the number of possible breach sizes when the leakage positions are p1, p2 and pa respectively.
Then, according to the results of table 2, the possible readings of all HF monitors in the plant are calculated separately for each (p, d), for each HF monitor there are Σ (b+c+ … … +e) preset data; assuming that there are f HF monitors, then there are Σ (b+c+ … … +e) f preset data for all HF monitors, see table 3, with table 3 as the preset data matrix;
table 3: all possible preset data
If the actual data from the HF monitor is x1 … … xf during an accident. The specific steps of the reverse thrust are as follows:
first, interpolation is performed to find possible (p, d) based on the position of the actual data x1 … … xf of each HF monitor in the preset data. Since the results of the long-distance large-size leak and the short-distance small-size leak may be similar at a certain HF monitor, the number of (p, d) found may be more than one, but several. The several (p, d) form a set, which is a union relationship. Such as the union obtained from the monitored data of m1, m2, … … mf, respectively, is shown in table 4.
Table 4 all possible (p, d)
In the above table, x and y … … z are the numbers (p, d) which are obtained and concentrated from the monitoring data of m1 and m2 … … mf, respectively.
Then, the leakage position and the break size are reversely deduced from the data of all HF monitors: the unique (p, d) is determined by taking the intersection again for all the union sets obtained in the previous step, see formula (1).
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (1)
1. A method of obtaining a leak location and a breach size in a leak, the method comprising the steps of:
(1) To UF in factory building 6 Carrying out pre-danger analysis on the leakage accident;
(2) Obtaining possible leakage positions and break sizes based on the analysis in the step (1);
(3) Calculating all possible leakage positions and breach sizes;
(4) Obtaining all readings of the HF monitor under the situation of possible accidents, and taking the readings as a preset data matrix;
(5) After the accident is over, interpolation is carried out according to the position of the HF monitoring data in a preset data matrix, and the leakage position and the crack size are reversely pushed; the method comprises the steps that a plurality of HF monitoring data are provided, the leakage position and the break size obtained based on the single HF monitoring data are not unique, and the union set of the leakage position and the break size obtained by the reverse thrust of each HF monitoring data is taken as an intersection, so that the unique leakage position and the unique break size are determined.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910431646.8A CN110287454B (en) | 2019-05-22 | 2019-05-22 | Method for acquiring leakage position and crack size in leakage accident |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910431646.8A CN110287454B (en) | 2019-05-22 | 2019-05-22 | Method for acquiring leakage position and crack size in leakage accident |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110287454A CN110287454A (en) | 2019-09-27 |
| CN110287454B true CN110287454B (en) | 2023-05-12 |
Family
ID=68002722
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910431646.8A Active CN110287454B (en) | 2019-05-22 | 2019-05-22 | Method for acquiring leakage position and crack size in leakage accident |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110287454B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111666655B (en) * | 2020-05-08 | 2023-07-14 | 中国辐射防护研究院 | Calculation method of uranium hexafluoride leakage source term |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106507781B (en) * | 2007-07-23 | 2010-12-15 | 中核兰州铀浓缩有限公司 | A kind of method that UF6 is collected in condensation |
| CN106730941A (en) * | 2016-12-28 | 2017-05-31 | 中核四0四有限公司 | The evaporation feeding device of HF in a kind of uranium conversion production process |
| CN109637680A (en) * | 2018-12-11 | 2019-04-16 | 中广核工程有限公司 | Nuclear power station leakage monitoring alarm method and alarm system |
-
2019
- 2019-05-22 CN CN201910431646.8A patent/CN110287454B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106507781B (en) * | 2007-07-23 | 2010-12-15 | 中核兰州铀浓缩有限公司 | A kind of method that UF6 is collected in condensation |
| CN106730941A (en) * | 2016-12-28 | 2017-05-31 | 中核四0四有限公司 | The evaporation feeding device of HF in a kind of uranium conversion production process |
| CN109637680A (en) * | 2018-12-11 | 2019-04-16 | 中广核工程有限公司 | Nuclear power station leakage monitoring alarm method and alarm system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN110287454A (en) | 2019-09-27 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106935303B (en) | A kind of filling splicer's process of spent fuel transport container | |
| CN116911619B (en) | Intelligent chemical production management and control system based on data analysis | |
| CN110287454B (en) | Method for acquiring leakage position and crack size in leakage accident | |
| CN113449955A (en) | Comprehensive pipe rack dangerous and sensitive pipeline safety assessment method based on fault tree analysis method | |
| CN104134160A (en) | Electric power system human factor reliability evaluation method based on CREAM model | |
| CN104651873A (en) | Intelligentized container modularized middle-temperature electrolytic fluorine-preparing device | |
| CN204229846U (en) | A kind of hydrogen system that disappears for small-sized steel containment vessel | |
| Nugraha et al. | Designing a SCADA system simulator for fast breeder reactor | |
| CN104591955A (en) | Preparation method of radioactive methyl iodide | |
| CN110555585A (en) | Automatic hidden danger level identification and alarm system for steel production equipment | |
| CN110390439A (en) | Oil field Early-warning Model system based on big data rough set theory | |
| CN104361917A (en) | Automatic radiochemical separation system used for measuring fuel consumption of spent fuel element | |
| CN105304149B (en) | Alpha contamination measurement flow in overhaul process of fuel defective unit of mega-kilowatt nuclear power plant | |
| CN114184231A (en) | Construction engineering construction site construction environment online monitoring method based on big data analysis | |
| CN204385299U (en) | Warm electrolysis fluorine device in intelligent freight container module type | |
| CN204204433U (en) | For the robotization Radiochemical Separation system of spent fuel element burnup measurement | |
| Lei et al. | The Evaluation Method of Uranium Hexafluoride Leakage Accident Release Source Term | |
| Kanik et al. | 3D analysis of hydrogen distribution and its mitigation using passive autocatalytic recombiners (PARs) inside VVER-1000 containment | |
| Nie | Comprehensive Evaluation of Rail Transit Hub Transfer Based on AHP | |
| ZHANG et al. | Validation and Evaluation of COSINE Software Package Based on the Operation Data of Third Generation Passive Pressurized Water Reactor | |
| Hsu et al. | The Model Establishment and Analysis of TRACE/MELCOR for Kuosheng Nuclear Power Plant Spent Fuel Pool | |
| Abdelrazek et al. | Investigation of the Capability of REALP5 to Solve Complex Fuel Geometry | |
| Salem et al. | Assessment of off-site consequences due to severe nuclear accident according to release pathway reduction mechanisms using computer code | |
| Li et al. | Construction and Application of Metal Equipment Supervision Management Information System | |
| Xiaolong et al. | Improvement and Application of Back Pressure Control Valve and Breathing Valve for Auxiliary Feedwater System in Nuclear Power Plant |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |