CN112633790B - Method for defining accident response boundary under situation of radioactive substance transportation fire accident - Google Patents
Method for defining accident response boundary under situation of radioactive substance transportation fire accident Download PDFInfo
- Publication number
- CN112633790B CN112633790B CN202011389133.4A CN202011389133A CN112633790B CN 112633790 B CN112633790 B CN 112633790B CN 202011389133 A CN202011389133 A CN 202011389133A CN 112633790 B CN112633790 B CN 112633790B
- Authority
- CN
- China
- Prior art keywords
- accident
- radioactive
- radius
- defining
- limit value
- 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
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/08—Logistics, e.g. warehousing, loading or distribution; Inventory or stock management
- G06Q10/083—Shipping
- G06Q10/0832—Special goods or special handling procedures, e.g. handling of hazardous or fragile goods
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/167—Measuring radioactive content of objects, e.g. contamination
-
- 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
Abstract
The invention provides a method for defining an accident response boundary under the condition of a radioactive substance transportation fire accident, which comprises the steps of S1, estimating the release amount of radioactive substances under the condition of the accident; s2, according to the release amount estimated in the step S1, an initial isolation radius R1 according to the chemical toxicity in the radioactive substance is given; s3, according to the release amount estimated in the step S1 and corresponding to the public dose limit value under the accident condition, providing an accident response radius R2 estimated according to the accident radiation consequence; s4, corresponding to the initial isolation radius R1 and the accident response radius R2, giving an accident response boundary Ra under the condition of the radioactive substance transportation fire accident; s5, according to the field meteorological condition and diffusion direction, the actual monitoring concentration of radioactive substance in the environment, and according to the chemical toxicity concentration limit value PAC1 level, giving out the 'protection action distance Rb'.
Description
Technical Field
The invention relates to the technical field of radioactive materials, in particular to a method for defining an accident response boundary under the situation of a radioactive substance transportation fire and explosion accident.
Background
In the non-radioactive field of China, in dangerous chemical transportation accidents, accident center areas, accident possible spread areas and accident possible influence areas are generally divided according to the damage range and the damage degree of accidents caused by chemicals and the positions of dangerous chemical accident sources.
Dangerous chemicals having chemical toxicity may occur in accidents such as leakage, fire and fire, in which there are both risks due to leakage of chemicals and safety problems due to fire or fire. The first 30 minutes of an accident with dangerous chemicals having chemical toxicity means the initial stage of the accident. If necessary rescue actions and measures can be taken as soon as possible in the stage, the method has an important effect on minimizing casualties and accident hazards.
A chemical accident emergency rescue response manual ERG2008 is jointly compiled in the United states, Canada and Mexico, the manual adopts the latest release rate and diffusion model, counts data of a hazardous substance accident reporting system of the United states department of transportation, and is comprehensively formed through meteorological observation data analysis, chemical substance toxicology contact data analysis and the like in more than 20 regions of the United states, Canada and three countries of Mexico for more than a plurality of years, and the manual has strong scientificity and guidance.
ERG2008 provides two data of 'initial isolation distance' and 'protective action distance' for assisting field decision of a chemical accident field, and when some scholars in China use the field decision method to research ammonia, chlorine and cyanogen leakage, under two different scenes of day and night, an 'emergency isolation area' and an 'evacuation radius' are estimated according to the loading amount and the leakage amount.
A great deal of research is also carried out on transport accidents in the radioactive field of China, the mode and the method mainly pay attention to the radiation influence of transported articles, the influence of transport personnel and the evaluation of accident consequences are mainly concerned, and a symptom suggestion draft of an HAD guide of radioactive article transport nuclear and radiation accident emergency preparation and emergency response is issued only in 2018 in an accident response part, and only the evaluation of the radiation accident consequences is considered in the guide. And the accident scene is firstly subjected to ' evaluation of potential radioactivity and related hazards ', and the definition of ' limited access areas and internal warning lines ' is carried out in the accident control stage, wherein the definition of the ' internal warning areas ' is that the evacuation distance is 300 meters according to the radiation level (external gamma is more than 100 MuSv/h) or the place determined according to the radioactive substance transport nuclear and radiation accident response guideline '. The estimation and the setting of the evacuation distance only consider the radiation hazard of radioactive substances, and the chemical characteristics of a large amount of leaked radioactive transportation materials with chemical toxicity are not set, so that the environmental risks possibly caused under the condition of fire accidents in the transportation of some radioactive substances are ignored.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a method for defining an accident response boundary under the situation of a radioactive substance transportation fire accident, which comprehensively considers the chemical toxicity of chemicals in the surrounding environment caused by the release of radioactive substances, and in the response region division under the accident situation, the initial isolation distance is set not only according to the evaluation result of the radiation accident consequence, but also comprehensively considers the chemical toxicity of the released radioactive substances, and the corresponding accident response boundary and the protection action distance are given after comprehensively considering the two distances.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a method of demarcating an accident response boundary in a radioactive material transport fire accident scenario, the method comprising:
s1, estimating the release amount of radioactive substances under accident conditions;
s2, according to the release amount estimated in the step S1, the initial isolation radius R1 according to the chemical toxicity in the radioactive substance is given;
s3, according to the release amount estimated in the step S1, corresponding to the public dose limit value under the accident condition, an accident response radius R2 estimated according to the accident radiation consequence is given;
s4, corresponding to the initial isolation radius R1 and the accident response radius R2, giving an accident response boundary Ra under the condition of the radioactive substance transportation fire accident;
s5, according to the field meteorological conditions, the diffusion direction and the actual monitoring concentration of radioactive substances in the environment, the 'protective action distance Rb' is given according to the chemical toxicity concentration limit value PAC1 level; after a fire accident occurs, according to on-site meteorological conditions and wind direction, at a certain distance downwind of a main wind direction, according to the release amount of radioactive substances, an ambient air monitoring point is arranged, according to the actually monitored environmental concentration value of the radioactive substances, a measured radius is given corresponding to a PAC 1-level protection action limit value, and therefore a protection action distance Rb is correspondingly given.
In some embodiments, in the above step S4, wherein when R1< R2, R1 is selected as Ra; when R1 ≧ R2, R2 was selected as Ra.
In some embodiments, in the step S1, the mass concentration distribution of the radioactive materials in the fire accident at different distances is estimated according to the fuel composition of the vehicle fuel tank, the loading capacity of the vehicle and the type of the loaded transportation materials in the accident situation, and according to the release parameters ARF of the radioactive materials and the respirable fraction RF of the people in the fire accident situation.
In some embodiments, the release parameter ARF is 2.34 x 10-4-7.18×10-4(ii) a The inhalable fraction RF is 1.61 x 10-6-1.56×10-4。
In some embodiments, at the time of defining the initial isolation radius R1, the smaller concentration value of the acute inhalation concentration limit and the protection action limit PAC3 of 10mg of soluble uranium is selected as the ground concentration value corresponding to the initial isolation radius, and the initial isolation radius R1 is defined.
In some embodiments, the accident response radius R2 is defined in consideration of the external irradiation and the inhalation internal irradiation in the radioactive influence pathway, with the public acute irradiation dose limit of 5msv or 10msv as the dose estimation limit under the accident condition, according to the release amount of the radioactive material given in the above step S1.
The invention has the beneficial effects that: the method comprehensively considers the chemical toxicity of chemicals in the surrounding environment caused by the release of radioactive substances, not only according to the evaluation result of the radiation accident consequence, but also comprehensively considers the initial isolation distance set by the chemical toxicity of the released radioactive substances in the response region division under the accident situation, and gives corresponding 'accident response boundary' and 'protection action distance' after comprehensively considering the two distances.
Drawings
Fig. 1 is a schematic flow chart of the defining method in the present embodiment.
Fig. 2 is a schematic structural diagram of the defining method in the present embodiment.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
Referring to fig. 1 to 2, the present embodiment provides a method for defining an accident response boundary in a radioactive material transportation fire accident scenario, including:
s1, estimating the release amount of radioactive substances under accident conditions;
estimating the mass concentration distribution conditions of radioactive materials at different distances under the fire accident according to the fuel components of a vehicle oil tank, the loading capacity of the vehicle and the types of loaded and transported materials under the accident condition, and according to the release parameters ARF of the radioactive materials and the respirable fraction RF of personnel under the fire accident condition; in some embodiments, the release parameter ARF is 2.34 × 10-4-7.18×10-4(ii) a Inhalable fraction RF is 1.61X 10-6-1.56×10-4。
S2, according to the release amount estimated in the step S1, the initial isolation radius R1 according to the chemical toxicity in the radioactive substance is given;
in the transportation of radioactive materials, there are uranium-containing materials and spent fuels, and many radioactive material types are contained therein. Taking the example of transporting radioactive materials as uranium substances, the chemical toxicity of uranium generally considers the internal irradiation health effect that can be caused after a person can inhale uranium. When The initial isolation radius is divided, an acute inhalation concentration limit of 10mg of soluble uranium and a smaller concentration value in a Protective action limit PAC3 given by American SCAPA ((The Subcommittee on sequence Assessment and Protective Actions) referring to an acute irradiation guidance level of EPA) are selected as a ground concentration value corresponding to The initial isolation radius, and The initial isolation radius R1 is divided; where PAC (Protective Action criterion) limits. PAC grade 1 indicates a slight, transient effect on human health; and 2, stage: may have irreversible or other serious health effects that may affect the person taking protective measures; and 3, level: the influence on human body is the biggest, can produce the health influence of life-threatening.
S3, according to the release amount estimated in the step S1, corresponding to the public dose limit value under the accident condition, an accident response radius R2 estimated according to the accident radiation consequence is given;
according to the amount of radioactive material released as given in S1, "accident response radius R2" is defined in consideration of external irradiation and inhaled internal irradiation in the radioactive influence route, and dose influence on the public in the accident, taking the public acute irradiation dose limit of 5mSv or 10mSv under the accident condition as a dose estimation limit.
S4, a corresponding initial isolation radius R1 and an accident response radius R2, an accident response boundary Ra under the condition of the radioactive substance transportation fire accident is given,
when R1< R2, R1 is selected as Ra;
when R1> R2, R2 is selected as Ra;
it should be noted that the set of "accident response boundaries Ra" is the boundary condition that is most conservative under the most adverse meteorological conditions, and can give an initial boundary value when a transportation accident emergency response report is compiled before the radioactive substance is transported.
The boundary values are defined without regard to meteorological conditions, actual concentration monitoring values and other objective conditions during transportation.
S5, according to the field meteorological conditions, the diffusion direction and the actual monitoring concentration of radioactive substances in the environment, the 'protective action distance Rb' is given according to the chemical toxicity concentration limit value PAC1 level;
after a fire accident occurs, according to on-site meteorological conditions and wind direction, at a certain distance downwind of a main wind direction, according to the release amount of radioactive substances, an ambient air monitoring point is arranged, according to the actually monitored environmental concentration value of the radioactive substances, a measured radius is given corresponding to a PAC 1-level protection action limit value, and therefore a protection action distance Rb is correspondingly given.
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.
Claims (5)
1. A method for defining an accident response boundary in a radioactive material transportation fire accident scenario, the method comprising:
s1, estimating the release amount of radioactive substances under accident conditions;
in the step S1, the mass concentration distribution of the radioactive material in the fire accident at different distances is estimated according to the fuel component of the vehicle fuel tank, the loading capacity of the vehicle and the type of the loaded transportation material in the accident situation, and according to the release parameter ARF of the radioactive material and the respirable fraction RF of the people in the fire accident situation;
s2, according to the release amount estimated in the step S1, the initial isolation radius R1 according to the chemical toxicity in the radioactive substance is given;
s3, according to the release amount estimated in the step S1, corresponding to the public dose limit value under the accident condition, an accident response radius R2 estimated according to the accident radiation consequence is given;
s4, corresponding to the initial isolation radius R1 and the accident response radius R2, giving an accident response boundary Ra under the condition of the radioactive substance transportation fire accident;
when the initial isolation radius R1 is defined, selecting a smaller concentration value of an acute inhalation concentration limit value and a protection action limit value PAC3 of soluble uranium as a ground concentration value corresponding to the initial isolation radius, and defining an initial isolation radius R1;
according to the release amount of the radioactive material given in the step S1, considering external irradiation and inhalation internal irradiation in the radioactive influence path, and defining an accident response radius R2 by taking a public acute irradiation dose limit value under an accident condition as a dose estimation limit value;
s5, according to the field meteorological conditions, the diffusion direction and the actual monitoring concentration of radioactive substances in the environment, the 'protective action distance Rb' is given according to the chemical toxicity concentration limit value PAC1 level; after a fire accident occurs, according to on-site meteorological conditions and wind direction, at a certain distance downwind of a main wind direction, according to the release amount of radioactive substances, an ambient air monitoring point is arranged, according to the actually monitored environmental concentration value of the radioactive substances, a measured radius is given corresponding to a PAC 1-level protection action limit value, and therefore a protection action distance Rb is correspondingly given.
2. The method for defining an accident response boundary in the event of a radioactive material transportation fire accident according to claim 1, wherein in step S4, when R1< R2, R1 is selected as Ra; when R1 ≧ R2, R2 was selected as Ra.
3. The method for defining the accident response boundary in the event of a radioactive substance transportation fire accident according to claim 2, wherein the release parameter ARF is 2.3410-4-7.18×10-4(ii) a The inhalable fraction RF is 1.61 x 10-6-1.56×10-4。
4. The method for defining the accident response boundary in the case of a radioactive substance transportation fire accident according to claim 1, wherein the acute absorption concentration limit of soluble uranium is 10 mg.
5. The method for defining the accident response boundary in the case of a radioactive substance transportation fire accident according to claim 1, wherein the public acute exposure dose limit value under the accident condition is 5msv or 10 msv.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011389133.4A CN112633790B (en) | 2020-12-02 | 2020-12-02 | Method for defining accident response boundary under situation of radioactive substance transportation fire accident |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011389133.4A CN112633790B (en) | 2020-12-02 | 2020-12-02 | Method for defining accident response boundary under situation of radioactive substance transportation fire accident |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112633790A CN112633790A (en) | 2021-04-09 |
| CN112633790B true CN112633790B (en) | 2022-05-20 |
Family
ID=75307388
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202011389133.4A Active CN112633790B (en) | 2020-12-02 | 2020-12-02 | Method for defining accident response boundary under situation of radioactive substance transportation fire accident |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112633790B (en) |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002022839A (en) * | 2000-07-03 | 2002-01-23 | Aloka Co Ltd | Radiation-measuring apparatus |
| WO2014085081A1 (en) * | 2012-11-12 | 2014-06-05 | Canberra Industries, Inc. | Radiation analysis system and method |
| CN103903105A (en) * | 2014-04-21 | 2014-07-02 | 苏州热工研究院有限公司 | Nuclear accident consequence assessment and auxiliary decision integrated platform and method |
| CN104992292A (en) * | 2015-06-30 | 2015-10-21 | 合盛硅业股份有限公司 | Emergency rescue method of accident of methylchlorosilane production system |
| CN105247593A (en) * | 2014-04-17 | 2016-01-13 | 深圳市大疆创新科技有限公司 | Flight control for flight-restricted regions |
| CN106096829A (en) * | 2016-06-06 | 2016-11-09 | 浙江大学 | A kind of petroleum chemical enterprise accident risk loss appraisal method |
| CN106919789A (en) * | 2017-02-16 | 2017-07-04 | 中国环境科学研究院 | The norm of nonparametric kernel density of unexpected environmental accident emergency disposal limit value determines method |
| CN108960542A (en) * | 2017-05-18 | 2018-12-07 | 中国辐射防护研究院 | A kind of determination method of the acceptable degree of radioactive substance risk in transit |
| CN109613589A (en) * | 2018-11-12 | 2019-04-12 | 中国辐射防护研究院 | One kind being used for nuclear facilities damage sequence public toxic effect evaluation method |
| 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 |
-
2020
- 2020-12-02 CN CN202011389133.4A patent/CN112633790B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002022839A (en) * | 2000-07-03 | 2002-01-23 | Aloka Co Ltd | Radiation-measuring apparatus |
| WO2014085081A1 (en) * | 2012-11-12 | 2014-06-05 | Canberra Industries, Inc. | Radiation analysis system and method |
| CN105247593A (en) * | 2014-04-17 | 2016-01-13 | 深圳市大疆创新科技有限公司 | Flight control for flight-restricted regions |
| CN103903105A (en) * | 2014-04-21 | 2014-07-02 | 苏州热工研究院有限公司 | Nuclear accident consequence assessment and auxiliary decision integrated platform and method |
| CN104992292A (en) * | 2015-06-30 | 2015-10-21 | 合盛硅业股份有限公司 | Emergency rescue method of accident of methylchlorosilane production system |
| CN106096829A (en) * | 2016-06-06 | 2016-11-09 | 浙江大学 | A kind of petroleum chemical enterprise accident risk loss appraisal method |
| CN106919789A (en) * | 2017-02-16 | 2017-07-04 | 中国环境科学研究院 | The norm of nonparametric kernel density of unexpected environmental accident emergency disposal limit value determines method |
| CN108960542A (en) * | 2017-05-18 | 2018-12-07 | 中国辐射防护研究院 | A kind of determination method of the acceptable degree of radioactive substance risk in transit |
| CN109613589A (en) * | 2018-11-12 | 2019-04-12 | 中国辐射防护研究院 | One kind being used for nuclear facilities damage sequence public toxic effect evaluation method |
| 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 |
Non-Patent Citations (4)
| Title |
|---|
| "Manual for first responders to a radiological emergency";E PREP;《www-pub.iaea.org/MTCD/publications/PDF/epr_Firstresponder_web.pdf》;20061031;第1-86页 * |
| "惠州李长荣橡胶有限公司突发环境事故应急预案";惠州李长荣橡胶有限公司;《www.dayawan.gov.cn/dywzdly/wryjc/201606/79bd495e727549d4b86f4076a020229d/files/1e6a9518ef8f4221a4221640e2854cce.pdf》;20140630;第1-67页 * |
| "液氨储罐灾难性破裂事故隔离区域划分研究";蒲春晓;《中国优秀硕士学位论文全文数据库 (工程科技Ⅰ辑)》;20200715;第B016-68页 * |
| "用于六氟化铀泄漏事故后果评估的化学物质推荐限值";潘伟 等;《辐射防护》;20170520;第37卷(第3期);第230-234页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN112633790A (en) | 2021-04-09 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Nakayama et al. | Simulation-based safety investigation of a hydrogen fueling station with an on-site hydrogen production system involving methylcyclohexane | |
| Saji | A post accident safety analysis report of the Fukushima Accident—future direction of evacuation: lessons learned | |
| Levenson et al. | Realistic estimates of the consequences of nuclear accidents | |
| CN112633790B (en) | Method for defining accident response boundary under situation of radioactive substance transportation fire accident | |
| CN112651598B (en) | Method for defining accident response boundary under radioactive substance transportation explosion accident scene | |
| CN108960542A (en) | A kind of determination method of the acceptable degree of radioactive substance risk in transit | |
| Hayes | A summary of accidents and incidents involving radiation in atomic energy activities, June 1945 through December 1955 | |
| Cohen | Impacts of the Nuclear Energy Industry on Human Health and Safety: Evaluation of the hazards of various stages of power production, coupled with analysis of existing data on radiation effects, permits experts to predict the magnitude of the risk involved in an all-nuclear energy economy | |
| Bevelacqua | The three Mile Island, Chernobyl, and Fukushima Daiichi accidents and their radiological impacts | |
| Elkhatib et al. | Modeling of atmospheric dispersion and radiation dose for a hypothetical accident in radioisotope production facility | |
| McLendon | Accidental Radiation Excursion at the Oak Ridge Y-12 Plant—II: Health Physics Aspects of the Accident | |
| Board | Criteria for Planning, Preparedness and Response Nuclear or Radiological Emergency | |
| Arlouski et al. | Risks to the population life activity as a result of manmade accidents with the emissions of radionuclides | |
| Polat et al. | On the Modeling of Wildfires-Induced Release and Atmospheric Dispersion in Radioactively Contaminated Regions | |
| Sanderson et al. | Review of past nuclear accidents: source terms and recorded gamma-ray spectra | |
| Larsen et al. | Radiation emergency response in Illinois, Alabama, and Texas | |
| Büttner et al. | REVIEW OF MATERIAL REQUIREMENTS OF THE IAEA TRANSPORT REGULATIONS FOR LSA-II AND LSA-III | |
| Rosli | Chernobyl Nuclear Disaster | |
| Meiliasari et al. | The concept of an early warning system for the use of nuclear technology in Indonesia | |
| Kripps | TMI-2 reactor building purge: Kr-85 venting | |
| Westerman | Transportation issues in nuclear medicine and the release of radioactivity into the environment | |
| Sert et al. | Assessment of safety distances to be implemented in case of accident in radioactive material transportation | |
| Weaver | A Review of Accident Risks in Light-Water-Cooled Nuclear Power Plants | |
| Biello | It’s not just Fukushima: mass disaster evacuations challenge planners | |
| Berthold et al. | Criteria for confinement of radioactive debris of Chernobyl NPP Fourth Power Unit |
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 |