CN110133705A - A kind of estimation of activity method and apparatus of nuclear power station radioactive substance - Google Patents
A kind of estimation of activity method and apparatus of nuclear power station radioactive substance Download PDFInfo
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Abstract
The present invention relates to nuclear power station Radiation monitoring and protection technology fields, provide the activity estimation method and device of a kind of nuclear power station radioactive substance, are related to radioactive substance transport field.It is spherical container due to carrying out equivalent conversion by the container to storage of radioactive material, the equivalent shield thickness that the spherical container of the storage container is calculated using isometric principle estimates the activity of radioactive substance in the physical attribute according to equivalent shield thickness and radioactive substance.Because the estimation of the equivalent shield thickness is reasonable, so that the estimation of radioactive substance activity is more acurrate, more reliable and more credible.On the one hand nuclear power station can be reduced or remitted other unit need to be entrusted to be estimated, on the other hand can the domestic radioactive substance transport of specification estimation of activity method, and then improve international image in the art.
Description
Technical field
The present invention relates to nuclear power station Radiation monitoring and protection technology fields, and in particular to a kind of nuclear power station radioactive substance
Estimation of activity method and apparatus.
Background technique
The U.S. and is most ground early in technical security target in the world earliest by the country of npp safety target quantification
Study carefully the middle country that will determine that the method for discussing combines with probability theory method.After three miles of island nuclear accident in 1979, U.S.'s core pipe meeting
(NRC) research of quantitative safety goal has been carried out.NRC proposes two quantitative security targets (quantitative health objectives), this is just
Be " two one thousandths " often said: 1) reactor accident is issuable acute to a Salopian group near nuclear power plant
The 0.1% of the acute death risk being generally subject to due to other accidents is not to be exceeded in mortality risk；2) reactor accident is to core
A Salopian group issuable advanced stage (cancer) mortality risk of near power station is not to be exceeded since other reasons generate
Risk of cancer 0.1%." the nuclear power plant's basic security principle " that IAEA was published in 1988 clearly proposes Nuclear Safety target
It is made of overall goal and two objectives, objectives are radiation protection target and technical security target.In technical security
In target statement, corresponding quantitative objective is proposed to operation and new nuclear power factory respectively.Reactor core probability of damage (CDF) and radiation
Property largely in early days discharge probability (LERF).Quantitative technique security target in INSAG-12 be it is consistent with technical security target, it is existing
There is what the damage of serious reactor core occurred for nuclear power plant to be less than about 10 in probability every operation heap year-4, Severe accident management and mitigation strategy can
The probability of the extensive radioactivity release of early stage response outside factory will be needed at least to reduce an order of magnitude.Gradually, global core work
Industry tends to know together to the quantitative safety goal of nuclear power plant.But radioactive substance is transported, quantitative peace is not yet determined so far
Full target.
Radioactive substance is being transported including in-service radioactive source, retired Spent Radioactive Source (object) and with the device of radioactive source
In defeated moving process, the safety in order to ensure radioactive substance and the radiation safety to surrounding enviroment on the way, according to country's " radiation
Property goods transportation safety management regulations " regulation, haulage vehicle needs to be equipped with necessary radiation monitoring device, burglary-resisting installation, right
One, the transportational process of two class radioactive substances will also realize on-line monitoring.Wherein the estimation of activity of radioactive substance is radioactivity
Important parameter in goods transportation.Domestic radioactive substance transport field at present, for estimation of activity even none system
One computation model, and the tool for facilitating radiation protection officer to estimate rapidly.Each nuclear power station is all that oneself is temporarily estimated roughly
It calculates or commission external unit assists estimation, cause to estimate intricate operation, and the estimation result difference of each family is huge.Especially put
When the internationally transport of penetrating property article, the query that domestic estimation of activity result is abroad gone together influences international image.
Summary of the invention
The present invention solves the technical problem of in radioactive substance transportational process the problem of estimation of activity.
According in a first aspect, providing a kind of activity estimation method of nuclear power station radioactive substance in a kind of embodiment, comprising:
Obtain the physical parameter of the container of storage of radioactive material；The physical parameter of the container includes container
Material, weight, length, width and height；
The equivalent shield thickness of container is obtained according to the physical parameter of the container；
Obtain the physical parameter of the radioactive substance；The physical parameter of the radioactive substance include material, it is default away from
It is thick from 1/10th shieldings of place's Environmental dose rate, exposure rate constant and the relatively described container material of the radioactive substance
Degree；
Radioactive substance is obtained according to the physical parameter of the radioactive substance and the equivalent shield thickness of the container
Activity.
Further, the equivalent shield thickness is that the spherical after the container body to be equivalent to a spherical cabinet is thick
Degree.
Further, the physical parameter according to the container obtains the equivalent shield thickness of container, comprising:
The equivalent shield thickness is obtained as follows:
Wherein, Δ r is equivalent shield thickness, and a is the length of container, and b is the width of container, and c is the height of container
Degree, M is the quality of container, and ρ is the material density of container, and π is pi.
Further, Environmental dose rate is Environmental dose rate at 1 meter at the pre-determined distance.
Further, described to be obtained according to the physical parameter of the radioactive substance and the equivalent shield thickness of the container
Radioactive substance activity, comprising:
Radioactive substance activity is obtained as follows:
Wherein, A is radioactive substance activity, and Δ r is equivalent shield thickness, and Dr is Environmental dose rate at pre-determined distance, and d is
For radioactive substance with respect to 1/10th shielding thickness of container material, Γ is exposure rate constant, the average ionization of W air
Energy.
According to second aspect, a kind of activity estimation device of nuclear power station radioactive substance is provided in a kind of embodiment, comprising:
Container physical parameter acquiring unit, the physical parameter of the container for obtaining storage of radioactive material；It is described
The physical parameter of container includes material, weight, length, width and the height of container；
Equivalent shield thickness acquiring unit obtains the equivalent shield of container for the physical parameter according to the container
Thickness；
The physical parameter acquiring unit of radioactive substance, for obtaining the physical parameter of the radioactive substance；It is described to put
The physical parameter of penetrating property substance includes material, Environmental dose rate, exposure rate constant and the radioactive substance at pre-determined distance
/ 10th shielding thickness of the relatively described container material；
Radioactive substance activity acquiring unit, for according to the radioactive substance physical parameter and the container
Equivalent shield thickness obtains radioactive substance activity.
Further, the equivalent thickness is the spherical face thickness being equivalent to the container body after one spherical cabinet；
The equivalent shield thickness acquiring unit obtains the equivalent shield thickness as follows:
Wherein, Δ r is equivalent shield thickness, and a is the length of container, and b is the width of container, and c is the height of container
Degree, M is the quality of container, and ρ is the material density of container, and π is pi.
Further, the radioactive substance activity acquiring unit obtains radioactive substance activity as follows,
Wherein, A is radioactive substance activity, and Δ r is equivalent shield thickness, and Dr is Environmental dose rate at pre-determined distance, and d is
For radioactive substance with respect to 1/10th shielding thickness of container material, Γ is exposure rate constant, the average ionization of W air
Energy.
According to the third aspect, a kind of activity estimation device of nuclear power station radioactive substance is provided in a kind of embodiment, comprising:
Memory, for storing program；
Processor, for the program by executing the memory storage to realize method described in first aspect.
According to fourth aspect, it includes program, described program that a kind of computer readable storage medium is provided in a kind of embodiment
It can be executed by processor to realize method described in first aspect.
The activity estimation method and device of a kind of nuclear power station radioactive substance according to above-described embodiment, it is contemplated that storage is put
The influence of the physical parameter of the container of penetrating property substance and the physical parameter of radioactive substance to radioactive substance activity, due to logical
The physical parameter of the physical parameter and radioactive substance of crossing container calculates radioactive substance activity, so that radioactive substance activity
It estimates more acurrate, more reliable.
Detailed description of the invention
Fig. 1 is a kind of estimation of activity method flow diagram of the radioactive substance of embodiment；
Fig. 2 is a kind of equivalent spherical cabinet schematic diagram of the container of embodiment；
Fig. 3 is the acquisition methods flow chart of transport index TI in embodiment a kind of；
Fig. 4 is a kind of flow chart of shipping label acquisition methods in embodiment；
Fig. 5 is a kind of structural schematic diagram of the estimation of activity device of radioactive substance in embodiment
Fig. 6 is the structural schematic diagram of the estimation of activity device of radioactive substance in another embodiment；
Fig. 7 is the interface schematic diagram of the estimation of activity device of radioactive substance in an embodiment.
Specific embodiment
Below by specific embodiment combination attached drawing, invention is further described in detail.Wherein different embodiments
Middle similar component uses associated similar element numbers.In the following embodiments, many datail descriptions be in order to
The application is better understood.However, those skilled in the art can recognize without lifting an eyebrow, part of feature
It is dispensed, or can be substituted by other elements, material, method in varied situations.In some cases, this Shen
Please it is relevant it is some operation there is no in the description show or describe, this is the core in order to avoid the application by mistake
More descriptions are flooded, and to those skilled in the art, these relevant operations, which are described in detail, not to be necessary, they
Relevant operation can be completely understood according to the general technology knowledge of description and this field in specification.
It is formed respectively in addition, feature described in this description, operation or feature can combine in any suitable way
Kind embodiment.Meanwhile each step in method description or movement can also can be aobvious and easy according to those skilled in the art institute
The mode carry out sequence exchange or adjustment seen.Therefore, the various sequences in the description and the appended drawings are intended merely to clearly describe a certain
A embodiment is not meant to be necessary sequence, and wherein some sequentially must comply with unless otherwise indicated.
It is herein component institute serialization number itself, such as " first ", " second " etc., is only used for distinguishing described object,
Without any sequence or art-recognized meanings.And " connection ", " connection " described in the application, unless otherwise instructed, include directly and
It is indirectly connected with (connection).
In embodiments of the present invention, according to the physical parameter of container and the physical parameter of radioactive substance to radioactive material
Matter activity is estimated, because the design feature in view of container carries out the calculating of equivalent shield thickness, so that radioactive substance
The estimation of activity is more acurrate, more reliable and more credible.
Embodiment one
Referring to FIG. 1, a kind of estimation of activity method flow diagram of the radioactive substance for embodiment, estimation of activity method packet
It includes:
Step 1 obtains the physical parameter of the container of storage of radioactive material.The physical parameter of container includes packaging
Material, weight, length, width and the height of case.Wherein the weight of container refers to the weight of container itself, does not include packaging
The weight of the stored substance of case.
Step 2 obtains the equivalent shield thickness of container according to the physical parameter of container.In one embodiment, equivalent screen
Covering thickness is the spherical face thickness being equivalent to container body after one spherical cabinet.Referring to FIG. 2, being a kind of collection of embodiment
It cases equivalent spherical cabinet schematic diagram, because the cause diversified in specifications of container is so we set length, width and the height of container
Degree is a, b and c respectively, and the quality and density of container are M and ρ.Container hypothesis is equivalent to a spherical shape by us, then spherical
The outer radius r1 of cabinet are as follows:
Wherein, r1 is equivalent spherical cabinet outer radius, and a is the length of container, and b is the width of container, and c is container
Height, π is pi.
Because the total volume that the volume of spherical cabinet is equal to container subtracts the volume of container material then:
Wherein, r1 is equivalent spherical cabinet inside radius, and a is the length of container, and b is the width of container, and c is container
Height, M is the quality of container, and ρ is the material density of container, and π is pi.
The then inside radius r2 of spherical cabinet are as follows:
Wherein, r1 is equivalent spherical cabinet inside radius, and a is the length of container, and b is the width of container, and c is container
Height, M is the quality of container, and ρ is the material density of container, and π is pi.
The then equivalent shield thickness deltat r of spherical cabinet are as follows:
Δ r=r1-r2
Wherein, Δ r is equivalent shield thickness, and a is the length of container, and b is the width of container, and c is the height of container
Degree, M is the quality of container, and ρ is the material density of container, and π is pi.
Step 3 obtains the physical parameter of radioactive substance.In one embodiment, the physical parameter of radioactive substance includes material
/ 10th shieldings of Environmental dose rate, exposure rate constant and radioactive substance with respect to container material at matter, pre-determined distance
Thickness.In one embodiment, Environmental dose rate is Environmental dose rate at 1 meter at pre-determined distance, can directly be surveyed by measuring tool
Amount obtains.For example, the material of container is iron, then iron is for 1/10th shielding thickness of common nucleic referring to following table:
| Nucleic | / 10th shielding thickness (mm) |
| Co60 | 67 |
| Cs137 | 50 |
Wherein, nucleic Co60 is Co 60, and nucleic Cs137 is Ce 137.
It is living to obtain radioactive substance according to the physical parameter of radioactive substance and the equivalent shield thickness of container for step 4
Degree.
Radioactive substance activity is obtained as follows:
Wherein, A is radioactive substance activity, and Δ r is equivalent shield thickness, and Dr is Environmental dose rate at pre-determined distance, and d is
For radioactive substance with respect to 1/10th shielding thickness of container material, Γ is exposure rate constant, the average ionization of W air
Energy.
The estimation formula of radioactive substance activity deduces process are as follows:
When shielding thickness is Δ r, predose rate Dr is shielded0Are as follows:
Wherein, Dr0It is shielding predose rate, Δ r is equivalent shield thickness, and Dr is Environmental dose rate at pre-determined distance, and d is
/ 10th shielding thickness of the radioactive substance with respect to container material.
When all positron-electrons that exposure refers to that photon releases in unit mass air are prevented from air,
The total charge dosage of the ion of the same symbol of generation, then exposure X are as follows:
Unit the roentgen R, 1R of exposure refer to 1cm3 (0.00129g) standard state (T=0 DEG C, P=760mmHg) air
In, secondary ionization total charge dosage that gamma-rays generates for 1 electrostatic unit exposure, for point source, exposure rate P:
Wherein, P is exposure rate, and A is radioactive substance activity, and Γ is exposure rate constant, and R is radioactive source to certain point
Distance, P is exposure rate.
Meeting electronic equilibrium, and under conditions of the bremsstrahlung that generates of secondary electron is ignored, Kerma is equal to
Exposure multiplied by air mean ionization energy.Absorbed dose and Kerma numerically equal, it may be assumed that
From the above, it can be seen that:
Wherein, A is radioactive substance activity, and Dr is Environmental dose rate at pre-determined distance, and Γ is exposure rate constant, and W is empty
The mean ionization energy of gas, Dr0 are shielding predose rates, and Δ r is equivalent shield thickness, and R is distance of the radioactive source to certain point, d
It is 1/10th shielding thickness of the radioactive substance with respect to container material.
When R takes 1 meter, be from one meter of radioactive source at, then radioactive substance activity A are as follows:
Wherein, A is radioactive substance activity, unit MBq；Δ r is equivalent shield thickness, unit m；Dr is environment at 1 meter
Dosage rate, unit mSvh-1；D is 1/10th shielding thickness of the radioactive substance with respect to container material, unit mm；Γ is
Exposure rate constant, unit are Cm2·kg-1B·q-1·s-1；The mean ionization energy of W air, unit are JC-1.In the formula
3.6×109It is the constant after Conversion of measurement unit, exposure rate constant Γ and radioactive material qualitative correlation, is as follows:
Wherein, nucleic Co60 is Co 60, and nucleic Cs137 is Ce 137.
For example, having a Co60 radioactive source activity is A MBq, then the local dosage rate Dr of distance 1m is how many mSv?
The first step searches exposure rate constant:
Γ=2.503 × 10-18(C·m2·kg-1·Bq-1·s-1)
Second step, the exposure rate P at R:
Third step calculates absorbed dose rate Dr:
Meeting electronic equilibrium, and under conditions of the bremsstrahlung that generates of secondary electron is ignored, Kerma is equal to
Exposure multiplied by air mean ionization energy.Absorbed dose and Kerma numerically equal.The mean ionization energy W=of air
33.68J/C。
1R=2.58 × 10-4C·Kg-1×33.68J·C-1
=0.00869JKg-1
=0.00869Gy
=8.69mGy
Dr=A × 3.49 × 10-5(R·h-1)×8.69mGy·R-1
=A × 30.328 × 10-5mGy/h
=A × 30.3208 × 10-5mSv/h
So for the source Co60, A (MBq)=0.033 × 105Dr (mSv/h).
Similarly, for the source Cs137, A (MBq)=0.13 × 105Dr (mSv/h).
During the actual shipment of radioactive substance, needs to fill in radioactive substance transport monitoring card, put in addition to filling in
Penetrating property substance activity, will also fill in the parameters such as transport index TI and shipping label.
The acquisition of transport index TI numerical value the following steps are included:
Step 1 determines at the outer surface 1m away from package, outer packing, cargo container or packless LSA-I or SCO-I
The horizontal Dr of maximum radiation (as unit of mSv/h), transport index should be the value multiplied by 100.For uranium ore and thorium ore and
The maximum radiation level of its concentrate, any point at the outer surface 1m away from tote can take:
0.4mSv/h is to uranium ore and thorium ore and its physical concentration object；
Chemical concentrate of the 0.3mSv/h to thorium；
Chemical concentrate of the 0.02mSv/h to uranium (except hex).
It is true to cope with step 1 for the transport index of tank, cargo container and packless LSA-I or SCO-I for step 2
Fixed value is modified multiplied by corresponding coefficient listed by table 1；
Step 3, according to the value that step 1 and step 2 are calculated answer after carry to decimal point first (such as will
1.2) 1.13 enter, only when calculated result is equal to or less than 0.05 just it is considered that transport index is zero.
It as described in Figure 3, is the acquisition methods flow chart of transport index TI in embodiment a kind of, it is first determined away from package, outside
Packaging, cargo container or packless LSA-I or SCO-I outer surface 1m at the horizontal Dr of maximum radiation, when tote most
Heavy in section area is less than 1m2When, transport index TI is 1 × 100Dr；When the area of tote maximum cross-section is less than 5m2It is greater than
1m2When, transport index TI is 2 × 100Dr；When the area of tote maximum cross-section is less than 20m2Greater than 5m2When, transport index TI
It is 3 × 100Dr；When the area of tote maximum cross-section is greater than 20m2When, transport index TI is 10 × 100Dr.When the fortune of acquisition
When the value of defeated index TI is not more than 0.05, transport index TI is set as 0.It is greater than after the value decimal point of the transport index TI of acquisition
One then using into a method taking one decimal place, i.e., after only taking decimal when the value 2 significant digits of transport index TI have value
One and only enters and do not give up.
The determination of shipping label is according to GB11806-2004 " radioactive substance transports regulation safely " in the 6.11st chapters and sections,
Package and outer packing should be divided into I grades (white), II grades of (Huang), III levels according to condition specified in table 2 and by following requirements
(Huang), as shown in the table:
Transport index meets a certain rank, and when surface emissivity level meets another rank, it should be the package or outsourcing
Dress incorporates the higher level-one of rank into.I grades (white) are minimum ranks.
It as described in Figure 4, is a kind of flow chart of shipping label acquisition methods in embodiment, wherein TI is transport index value, H
It is the maximum radiation level of any point on outer surface.
When TI value is that 0, H value is not more than 0.005, shipping label is I grades (white)；
When TI value is that 0, H value is greater than 0.005 and when less than 0.5, shipping label is II grades (Huang)；
When TI value is that 0, H value is greater than 0.5, shipping label is III level (Huang)；
When TI value is greater than 0 and is less than or equal to 1, H value no more than 0.5, shipping label is II grades (Huang).
In disclosed embodiments, carrying out equivalent conversion by the container to storage of radioactive material is spherical hold
Device calculates the equivalent shield thickness of the spherical container of the storage container using isometric principle, according to equivalent shield thickness and
The physical attribute of radioactive substance estimates radioactive substance activity.Because the estimation of the equivalent shield thickness is reasonable, so that
The estimation of radioactive substance activity is more acurrate, more reliable and more credible, on the one hand can reduce or remit nuclear power station need to entrust other unit into
Row estimation, on the other hand can specification domestic radioactive substance transport estimation of activity method, and then improve international in the art
Image.
Embodiment two
Referring to FIG. 5, for a kind of structural schematic diagram of the estimation of activity device of radioactive substance in embodiment, radioactive material
The estimation of activity device of matter includes container physical parameter acquiring unit 10, equivalent shield thickness acquiring unit 20, radioactive material
The physical parameter acquiring unit 30 and radioactive substance activity acquiring unit 40 of matter.Container physical parameter acquiring unit 10 is used for
Obtain the physical parameter of the container of storage of radioactive material.The physical parameter of container includes the material, weight, length of container
Degree, width and height.Equivalent shield thickness acquiring unit 20 is used to obtain the equivalent of container according to the physical parameter of container
Shielding thickness.Equivalent thickness is the spherical face thickness being equivalent to container body after one spherical cabinet.Equivalent shield thickness obtains
Unit is taken to obtain equivalent shield thickness as follows:
Wherein, Δ r is equivalent shield thickness, unit m；
A is the length of container, unit m；
B is the width of container, unit m；
C is the height of container, unit m；
M is the quality of container, units/kg；
ρ is the material density of container, and unit is Kgm3；
π is pi.
The physical parameter acquiring unit 30 of radioactive substance is used to obtain the physical parameter of radioactive substance.Radioactive substance
Physical parameter include material, the relatively described packaging of Environmental dose rate, exposure rate constant and radioactive substance at pre-determined distance
/ 10th shielding thickness of box lumber matter.In one embodiment, Environmental dose rate is Environmental dose rate at 1 meter at pre-determined distance, can
Directly to measure acquisition by measuring tool.Radioactive substance activity acquiring unit 40 is used to join according to the physics of radioactive substance
Several and container equivalent shield thickness obtains radioactive substance activity.Radioactive substance activity acquiring unit 40 is as follows
Radioactive substance activity is obtained,
Wherein, A is radioactive substance activity, unit MBq；
Δ r is equivalent shield thickness, unit m；
Dr is Environmental dose rate at 1 meter, unit mSvh-1；
D is 1/10th shielding thickness of the radioactive substance with respect to container material, unit mm；
Γ is exposure rate constant, and unit is Cm2·kg-1B·q-1·s-1；
The mean ionization energy of W air, unit are JC-1。
Embodiment three
Referring to FIG. 6, for the structural schematic diagram of the estimation of activity device of radioactive substance in another embodiment, radioactivity
The estimation of activity device of substance includes input unit 100, controller 200 and output device 300.Input unit is for inputting storage
The physical parameter of the container of radioactive substance and the physical parameter of radioactive substance.The physical parameter of container includes container
Material, weight, length, width and height.The physical parameter of radioactive substance includes material, Environmental dose rate, irradiation at 1 meter
/ 10th shielding thickness of dose rate constant and radioactive substance with respect to container material.Controller 200 is put for obtaining storage
The physical parameter of the container of penetrating property substance and the physical parameter of radioactive substance, and the physical parameter according to the container obtains
Take the equivalent shield thickness of container.In one embodiment, controller 200 obtains the equivalent shield thickness as follows:
Wherein, Δ r is equivalent shield thickness, and a is the length of container, and b is the width of container, and c is the height of container
Degree, M is the quality of container, and ρ is the material density of container, and π is pi.
Controller 200 obtains radioactive material according to the equivalent shield thickness of the physical parameter of radioactive substance and container again
Matter activity.In one embodiment, controller 200 obtains radioactive substance activity as follows:
Wherein, A is radioactive substance activity, and Δ r is equivalent shield thickness, and Dr is Environmental dose rate at 1 meter, and d is radiation
Property substance is with respect to 1/10th shielding thickness of container material, and Γ is exposure rate constant, the mean ionization energy of W air.
Output device 300 is for showing radioactive substance activity.In one embodiment, output device include display, loudspeaker,
LED display and/or intelligent terminal.
As shown in fig. 7, for the interface schematic diagram of the estimation of activity device of radioactive substance in an embodiment, an embodiment
In, the estimation of activity device of radioactive substance is intelligent terminal.Intelligent terminal is equipped with the Radiation monitoring software of radioactive substance,
Corresponding parameter input position inputs corresponding numerical value in software interface, then directly gives radioactive substance by intelligent terminal and live
Angle value.In one embodiment, intelligent terminal includes intelligent mobile terminal.
It will be understood by those skilled in the art that all or part of function of various methods can pass through in above embodiment
The mode of hardware is realized, can also be realized by way of computer program.When function all or part of in above embodiment
When being realized by way of computer program, which be can be stored in a computer readable storage medium, and storage medium can
To include: read-only memory, random access memory, disk, CD, hard disk etc., it is above-mentioned to realize which is executed by computer
Function.For example, program is stored in the memory of equipment, when executing program in memory by processor, can be realized
State all or part of function.In addition, when function all or part of in above embodiment is realized by way of computer program
When, which also can store in storage mediums such as server, another computer, disk, CD, flash disk or mobile hard disks
In, through downloading or copying and saving into the memory of local device, or version updating is carried out to the system of local device, when logical
When crossing the program in processor execution memory, all or part of function in above embodiment can be realized.
Use above specific case is illustrated the present invention, is merely used to help understand the present invention, not to limit
The system present invention.For those skilled in the art, according to the thought of the present invention, can also make several simple
It deduces, deform or replaces.
Claims (10)
1. a kind of activity estimation method of nuclear power station radioactive substance characterized by comprising
Obtain the physical parameter of the container of storage of radioactive material；The physical parameter of the container includes the material of container
Matter, weight, length, width and height；
The equivalent shield thickness of container is obtained according to the physical parameter of the container；
Obtain the physical parameter of the radioactive substance；The physical parameter of the radioactive substance includes material, at pre-determined distance
/ 10th shielding thickness of the relatively described container material of Environmental dose rate, exposure rate constant and the radioactive substance；
Radioactive substance activity is obtained according to the physical parameter of the radioactive substance and the equivalent shield thickness of the container.
2. the method as described in claim 1, which is characterized in that the equivalent shield thickness is that the container body is equivalent
For the spherical face thickness after a spherical cabinet.
3. method according to claim 2, which is characterized in that the physical parameter according to the container obtains container
Equivalent shield thickness, comprising:
The equivalent shield thickness is obtained as follows:
Wherein, Δ r is equivalent shield thickness, and a is the length of container, and b is the width of container, and c is the height of container, M
It is the quality of container, ρ is the material density of container, and π is pi.
4. the method as described in claim 1, which is characterized in that Environmental dose rate is environment agent at 1 meter at the pre-determined distance
Dose rate.
5. the method as described in claim 1, which is characterized in that the physical parameter according to the radioactive substance and described
The equivalent shield thickness of container obtains radioactive substance activity, comprising:
Radioactive substance activity is obtained as follows:
Wherein, A is radioactive substance activity, and Δ r is equivalent shield thickness, and Dr is Environmental dose rate at pre-determined distance, and d is radiation
Property substance is with respect to 1/10th shielding thickness of container material, and Γ is exposure rate constant, the mean ionization energy of W air.
6. a kind of activity estimation device of nuclear power station radioactive substance characterized by comprising
Memory, for storing program；
Processor, for the program by executing the memory storage to realize as described in any one of claims 1 to 5
Method.
7. a kind of computer readable storage medium, which is characterized in that including program, described program can be executed by processor with reality
The now method as described in any one of claims 1 to 5.
8. a kind of activity estimation device of nuclear power station radioactive substance characterized by comprising
Container physical parameter acquiring unit, the physical parameter of the container for obtaining storage of radioactive material；The packaging
The physical parameter of case includes material, weight, length, width and the height of container；
Equivalent shield thickness acquiring unit, the equivalent shield for obtaining container for the physical parameter according to the container are thick
Degree；
The physical parameter acquiring unit of radioactive substance, for obtaining the physical parameter of the radioactive substance；The radioactivity
The physical parameter of substance includes material, Environmental dose rate, exposure rate constant and the radioactive substance are opposite at pre-determined distance
/ 10th shielding thickness of the container material；
Radioactive substance activity acquiring unit, for according to the radioactive substance physical parameter and the container it is equivalent
Shielding thickness obtains radioactive substance activity.
9. device as claimed in claim 8, which is characterized in that the equivalent thickness is that the container body is equivalent to one
Spherical face thickness after spherical cabinet；It is thick that the equivalent shield thickness acquiring unit obtains the equivalent shield as follows
Degree:
Wherein, Δ r is equivalent shield thickness, and a is the length of container, and b is the width of container, and c is the height of container, M
It is the quality of container, ρ is the material density of container, and π is pi.
10. device as claimed in claim 8, which is characterized in that the radioactive substance activity acquiring unit is as follows
Radioactive substance activity is obtained,
Wherein, A is radioactive substance activity, and Δ r is equivalent shield thickness, and Dr is Environmental dose rate at pre-determined distance, and d is radiation
Property substance is with respect to 1/10th shielding thickness of container material, and Γ is exposure rate constant, the mean ionization energy of W air.
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