CN111191958B - Radiation protection optimization evaluation method suitable for radioactive substance transportation - Google Patents
Radiation protection optimization evaluation method suitable for radioactive substance transportation Download PDFInfo
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- 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
Abstract
The invention discloses a radiation protection optimization evaluation method suitable for radioactive substance transportation. The method uses the radiation protection efficiency value of radioactive substance transportation as an index to evaluate the radiation protection level of the radioactive substance transportation project. The radiation protection efficiency of radioactive transport is expressed as the sum of the annual collective doses of the workers divided by the product of the annual transport package total transport index and the total mileage shipped. The evaluation method provided by the invention can solve the difficulty that the radiation protection level between different types of radioactive transportation is difficult to evaluate, and better promotes the implementation of shippers in radiation protection optimization and improvement work.
Description
Technical Field
The invention relates to the technical field of radioactive substance transportation safety and radiation protection, in particular to a radiation protection optimization evaluation method suitable for radioactive substance transportation.
Background
Radiation protection optimization (ALARA) is an important item in a radiation protection three-principle system, is suitable for all nuclear activities, and also needs to be developed according to the ALARA principle in the radioactive substance transportation work. The ALARA has the general idea that firstly, the protection problem to be solved is clarified, a plurality of protection schemes are proposed, then various factors related to protection are found out, and quantitative or qualitative optimization analysis is carried out until the optimized protection scheme is obtained. However, ALARA works not only for optimization analysis and decision-making of protection schemes, but also for later re-optimization and improvement. Since the goals pursued by ALARA are not to achieve a certain fixed solution, the core idea is the continuous improvement of the protective action based on the advancement of capabilities and technology. It is therefore important to evaluate the effectiveness of radiation protection measures and to advance optimization. Radiation protection of nuclear power plants is one of the areas where optimization work is best implemented, and also benefits from the push of the international nuclear power operations association (WANO) for optimization work. A series of index systems are provided by combining WANO with the operating efficiency factor of the nuclear power station for experience feedback and improvement, wherein the protection efficiency is embodied by evaluating the radiation protection performance of all nuclear power generating units all over the world according to the index of 'normalized collective dose (man. Sv/GW. A)', so that ALARA work is promoted.
The transportation safety of radioactive substances is mobile nuclear practice, and the radiation protection is also one of important work of the transportation safety, and ALARA must be carried out. Due to the large difference of radiation levels of different types of radioactive goods, the evaluation and improvement of radiation protection effect between different radioactive transportation activities are difficult to implement.
The international agency for atomic energy (IAEA) in its publication "special safety regulations" sets forth a series of regulatory requirements and technical provisions for the safety and management of the transport of radioactive materials, and recommends that every member country in the world comply with the regulations. China also equally adopts the related technical requirements and index system of IAEA. Among them, IAEA proposes the concept of Transport Index (TI) for the radiation characteristic specific to radioactive parcels, which is indicated by the maximum radiation level at 1m outside the parcel. The index is a common characteristic value for all radioactive packages.
The shipper should perform personal dose monitoring on all personnel participating in the radiological transport activity. Therefore, the shipper can obtain the collective dose (man Sv) of the workers in the transportation activity through the whole-member dose monitoring result of a certain radioactive transportation item. Furthermore, the radiation effects of radioactive material transport are mainly contributed by both the package handling and the transport implementation. The radiation impact during loading and unloading is directly proportional to the number of packages handled and their Transport Index (TI), while the radiation dose during transport is directly related to the transport mileage (km).
With the rapid development of the nuclear energy industry in China, the radioactive substance transportation activities are more and more frequently developed. As a mobile verification practice, radioactive transport radiation protection is also one of the important jobs for transport safety, and shippers often have a series of radiation protection measures enacted to control and reduce personnel dosage, such as: decontamination of the surface of the goods package, shielding, arrangement of an isolation area, development of the radiation monitoring of the goods package and the dosage monitoring of personnel, formulation of dosage constraint, formulation of standard operation of operation procedures, enhancement of personnel technical training and the like. It must still be evaluated and continuously improved in compliance with the ALARA guidelines. The radioactive goods package conforms to the goods package classification management idea proposed by IAEA, establishes the national standard GB11806, manages according to the goods package classification idea, and classifies the radioactive goods package into IP type, A type, B type, C type and other types according to different contents.
There may be a difference of 3 to 4 orders of magnitude in the external dose rate for each type of package. Because of the great difference of the radiation level of the goods package, the corresponding protection measures and means are different, and the simple personnel dosage comparison cannot reflect the advantages and disadvantages of the radiation protection measures among transportation activities. Therefore, it has been difficult to perform radioprotection evaluation and optimization improvements between different radiological transport activities because there is no suitable method or index to perform cross-project optimization analysis and comparisons.
Therefore, how to obtain a method for comprehensively evaluating the effect of the radiation protection measures in the transportation activities of the radioactive goods packages of different types can make the radiation protection actions have the lowest personnel dosage as possible under the conditions of feasible technology, economy and reasonableness. This would be very significant for improving shippers' radiation protection management, advancing ALARA work, optimizing personnel dosage constraints, etc.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a radiation protection optimization evaluation method suitable for radioactive substance transportation. The method can solve the difficulty of difficult radiation protection evaluation between different radioactive transports, and better promote the implementation of shippers in radiation protection optimization and improvement work.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a radiation protection optimization evaluation method suitable for radioactive substance transportation uses a transportation radiation protection efficiency value as an index to evaluate the radiation protection level of a radioactive substance transportation project, and the calculation method of the transportation radiation protection efficiency value comprises the following steps:
(1) Obtaining annual collective dosage E of shipper S Human Sv;
(2) Acquiring a total transport index TI of a transport package all year round;
(3) Obtaining the total mileage D of the year round package transportation S ,km/a;
(4) Calculating the radiation protection efficiency V of transportation TRP (human Sv)/(TI km/a):
further, in the step (1), the method for acquiring the annual collective dosage ES of the carrier comprises the following steps: and carrying out personal dose monitoring of the whole personnel, summing all monitoring results according to measured personal dose monitoring measured values of all transport batches all the year round, and obtaining the annual collective dose ES of the personnel participating in the project carrier.
Further onIn the step (1), the annual collective dosage E of the carriers S The acquisition method comprises the following steps: monitoring the radiation level outside the cargo package during each transportation activity to obtain the positions 1m and 2m outside the cargo package and the dose rates of a cab and a living room, carrying out dose estimation according to the illuminated parameters of the shipper, and further summarizing to obtain the annual collective dose E of the shipper S 。
Furthermore, the total transport index TI of a package transported all year round is usually the sum of the number of packages transported all year round, but when taking a value of the transport index of a large package, it needs to consider whether the transport index value needs to be corrected by using an amplification factor.
Further, if the large package is loaded with a set of soft sub-packages, the total transportation index may conservatively take the sum of the transportation indexes of the sub-packages; if the large-sized cargo package is loaded with rigid sub-cargo package assemblies or bulk contents, the maximum radiation level measured at the position of 1m outside the large-sized cargo package is measured, and the correction result of the amplification factor is used as the total transportation index, wherein the amplification factor is related to the section size of the loaded cargo.
Further, the load size is less than or equal to 1m 2 When the amplification factor is 1; the size of the loaded material is more than 1m 2 And is less than or equal to 5m 2 When the amplification factor is 2; the size of the loaded material is more than 5m 2 And less than or equal to 20m 2 When the amplification factor is 3; the size of the loaded material is more than 20m 2 The amplification factor is 10.
The invention has the beneficial effects that:
the transportation radiation protection efficiency value can be used for the radiation protection optimization evaluation of all radioactive package type transportation items, can directly reflect the specific value relation among the package radiation level, the transportation amount and the radiation influence of the items, is suitable for the transverse comparison of the protection effect of crossing transportation activities and crossing package types, solves the difficulty that the radiation protection evaluation is difficult to different radioactive transportation, and better promotes the implementation of shippers in the radiation protection optimization and the improvement work.
Detailed Description
The present invention will be described in further detail with reference to specific embodiments.
A radiation protection optimization evaluation method suitable for radioactive substance transportation uses a transportation radiation protection efficiency value as an index to evaluate the radiation protection level of a radioactive substance transportation project, and the calculation method of the transportation radiation protection efficiency value comprises the following steps:
1) Carrier yearly collective dose acquisition
Annual collective dosage for shipper personnel E S The method can be obtained through two modes, firstly, the personal dose monitoring of the whole personnel is carried out, all monitoring results are summed according to the measured personal dose monitoring measured values of all transport batches in the whole year, and then the annual collective dose E of the personnel participating in the project is obtained S (ii) a The other method is to monitor the radiation level outside the parcel during each transportation activity, obtain the dose rates at the positions 1m and 2m outside the parcel and at the positions of a cab, a living room and the like, estimate the dose according to the receiving and irradiating parameters of the staff, and further sum up to obtain the annual collective dose ES of the staff. Wherein the first method has precedence over the second method.
2) Acquisition of total Transport Index (TI) of annual transport package
The total Transportation Index (TI) is typically the sum of the number of packages transported with the project throughout the year. However, when the transportation index of a large-sized package is taken into consideration, for example, when containers and other outer packages are used for concentrated loading, the applicability of the transportation index taking needs to be considered. If the set of soft subcontracts is loaded in the system, the sum of the transportation indexes of the subcontracts can be conservatively taken; if the container is a rigid sub-container set or a bulk content, the highest radiation level measured at the position of 1m outside the container is used as the transportation index, and the correction result of the amplification factor is used as the transportation index. The amplification factors were selected as shown in table 1.
TABLE 1 correction of the amplification factor of the transport index of large bales
Load articleCross-sectional dimension of | Amplification factor |
The size of the loaded material is less than or equal to 1m 2 | 1 |
1m 2 The size of the loaded article is less than or equal to 5m 2 | 2 |
5m 2 The size of the loaded material is less than or equal to 20m 2 | 3 |
The size of the loaded material is more than 20m 2 | 10 |
3) Acquisition of total mileage of package transportation
Total annual transportation mileage D S = single transport mileage x year transport batch
4) Transport radiation protection efficiency value (V) TRP ) Is derived from
Transport radiation protection efficiency (V) TRP ) Equal to the sum of the annual collective doses of the workers, divided by the product of the annual shipping package total shipping index (TI) and the total shipping mileage (km/a), and is expressed as follows:
in the formula, V TRP Radiation protection efficiency for transportation activities, in units of (man · Sv)/(TI · km/a);
es is the sum of the annual collective doses of the workers;
TI is the total shipping index of the annual shipping package;
ds is the total annual shipping mileage.
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 (3)
1. A radiation protection optimization evaluation method suitable for radioactive substance transportation is characterized by comprising the following steps: the method takes the transport radiation protection efficiency value as an index to evaluate the radiation protection level of the radioactive substance transport project, and the calculation method of the transport radiation protection efficiency value comprises the following steps:
(1) Obtaining annual collective dosage E of shipper S Human Sv;
(2) Acquiring a total transport index TI of a transport package all year round;
(3) Obtaining the total mileage D of the year round package transportation S ,km/a;
(4) Calculating the radiation protection efficiency V of transportation TRP (human Sv)/(TIkm/a):
in the step (2), the total transport index TI of the goods package transported all the year around is usually the sum of the number of the goods package transported all the year around, but when the transport index of the large goods package is taken as a value, whether the transport index value needs to be corrected by using an amplification factor or not needs to be considered; if the large-size package is loaded with a set of soft sub-packages, the total transportation index can be conservative to take the sum of the transportation indexes of the sub-packages; if the large-sized cargo package is loaded with rigid sub-cargo package assemblies or bulk contents, the maximum radiation level measured at the position of 1m outside the large-sized cargo package is measured, and the correction result of an amplification factor is used as a total transportation index, wherein the amplification factor is related to the section size of the loaded cargo; the size of the load is less than or equal to 1m 2 When the amplification factor is 1; the size of the loaded material is more than 1m 2 And is less than or equal to 5m 2 When the amplification factor is 2; the size of the loaded material is more than 5m 2 And less than or equal to 20m 2 When the amplification factor is 3; the size of the loaded material is more than 20m 2 The amplification factor is 10.
2. An evaluation method according to claim 1, characterized in that: in the step (1), the annual collective dosage E of the carriers S The acquisition method comprises the following steps: by carrying out personal dose monitoring of the whole personnel, summing all monitoring results according to measured personal dose monitoring measured values of all transport batches all the year round, and obtaining the annual collective dose E of the personnel participating in the project carrier S 。
3. An evaluation method according to claim 1, characterized in that: in the step (1), the annual collective dosage E of the shipper S The acquisition method comprises the following steps: monitoring the radiation level outside the cargo package during each transportation activity to obtain the positions 1m and 2m outside the cargo package and the dose rates of a cab and a living room, carrying out dose estimation according to the illuminated parameters of the shippers, and further summarizing to obtain the annual collective dose E of the shippers S 。
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