GB/T 16148-1995 Specification for estimation of radionuclide intake and internal radiation dose
Some standard content:
National Standard of the People's Republic of China
Specification for assessments ofintaaes and internal doses of radionuclide
Specificadon for assessments ofintaaes and internal doses of radionucliderySubject content and scope of application
This standard specifies the quick-lookup table for estimating radionuclide intake and internal doses. It is not applicable to occupational exposure after internal exposure. 2 Radiation protection evaluation of internal exposure
GB/T 16148-1995
2.1 The basis for evaluating the size of the deterministic effect of internal exposure on the irradiated device (tissue): the small amount of accumulated device (red tissue) dose it produces to the present. 1.1 It must satisfy the following relationship: Hn.- 0. 5 Sv
2.2 The basic quantity for evaluating the random effects of internal radiation on the whole body is the accumulated effective dose produced by it. It should satisfy the following relationship:
I.oe . 0. 05 Sv
2.3 For the same worker, it should be ensured that the Ha. and I2o.L produced by the ingested radionuclides are equal to their corresponding annual limit values, that is, to ensure that formulas (1) and (2) are simultaneously established. 2.4 The annual intake value is the drinking level limit value for evaluating internal radiation and is a more practical basis for evaluating the size of internal radiation. The intake evaluation can replace the evaluation of internal radiation doses. When evaluating the annual intake value, the following relationship should be met: 11, ALI (when a single type of nuclide is introduced)
The total activity of nuclides introduced into the human body in any way in any year, Bq: Where Www.bzxZ.net
is the corresponding annual intake limit of the nuclide in that way, B: Or. The following relationship should be met:
≤ (when a compound containing several nuclides is introduced) 2.5 When a mixture of different nuclides is introduced, the total internal exposure should meet the following relationship: Au
Where: is the number of types of nuclides introduced into the human body:
is the number of types of nuclides introduced into the human body:
is the total activity of nuclides introduced into the human body in any year, 3: 1) The annual intake limit of all types of nuclides can be found in (31702-81 Basic Standard for Health Protection during Radioactivity. State Bureau of Technical Supervision, 1995-12-15 Approved 622
(5)
1996-07-01 implementation
CB/T16148-1995
-year total activity of inhaled radium:, for the blue intake limit of nuclides through ingestion, BA; for the annual proposed intake limit of nuclides through inhalation, HI2. 6 When the internal and external radiation is not received within a year, the above relationship (1) and the following relationship (6) are satisfied: [e] + atasis
++++++++++++++++++++++++++ (6)
In the formula, the effective dose of external radiation received in the year is mw3 internal radiation monitoring amount
3.1 There are two types of internal radiation monitoring methods: In vivo measurement: in vitro direct measurement of the effective radioactive nuclei in the whole body or organs. For example: whole body counter measurement, median pulse measurement, joint measurement, etc.
b In vitro measurement; the activity of radioactive shuttles in human excreta (urine, urine, etc.). 3.2 The advantages of in vivo measurement are rapidity and convenience. They are suitable for monitoring a part of the body that emits X-rays, 7 or high-energy P-rays. The advantage of in vitro measurement is that the cost is relatively low, and it is also suitable for monitoring radionuclides that do not emit X-rays, ? or high-energy self-radiation. In general, these two methods are not mutually exclusive, but should be complementary. 3.3 The use of personal air samplers to measure the air pollution in the breathing zone of personnel can also be used as a good auxiliary means to directly estimate the inhaled dose.
3.4 Where the work is carried out, if the analysis of the particle size composition of the respiratory air can be carried out at the same time, the accuracy of the internal radiation dose evaluation of inhaled nuclides can be improved.
4 Estimation of intake
4.1 Based on the results of various internal radiation measurements, it is necessary to use a certain number of dynamic and biological composition of the representative models. These models can be used to describe the dynamic process of the accumulation, transfer and dissemination of radioactive elements in the body, and the data can be derived from the retention function or the input excretion function. 4.2 The specific calculation of intake can be carried out using the following formula: =R
The calculated intake is obtained by Hn!
M· The internal radiation monitoring value corresponding to the time after the intake (the result of in vivo measurement or in vitro measurement), BF and the extreme intake excretion function value or intake excretion function value RE of the monitoring item corresponding to the above-mentioned person and time -
The calculation example of intake is shown in Appendix B, and some IRF values are shown in Table E2. 4.3 When the date of occurrence of the intake event cannot be determined, half of the measurement period can be used to represent the approximate time from the intake to the monitoring.
4.4 When the ingested substance is known to have a different route of entry (preferably not a single ingestion) than the conditions for deriving the intake retention and excretion function, the intake estimate should be verified using the method specified in the reference literature [1-, pages D757-B763, in the Appendix.
4.5 When conditions permit, the metabolic data of the individual should be collected to verify and correct the general retention and excretion function derived from the reference model.
4.6 Once the intake is calculated, the intake evaluation can be made according to the provisions of 2.4 or 2.5 or 2.5. 4.7 Since the results of internal exposure monitoring are often accompanied by large statistical fluctuations, and the fluctuations and differences in the metabolic patterns of individuals will have a greater impact on the estimated results, if living conditions permit, multiple excreta sampling or in vivo measurements should be carried out over a longer period of time (i.e., within an interval that can be compared with the effective reduction period of the nuclide in the body) as much as possible, and then the following formula is used to obtain the best estimate of the intake amount:
Wu Zhong: 1
The best estimate of the intake basis, D:
(IRF):-
CB/T 1614B: 1995
Z[(IRF)A.]
B: The corresponding intake retention (or report) function value at the time of sampling or measurement: A: —Measured value of the first sampling + By
For an example of the best estimate of the intake amount, see the record. Estimation of internal radiation dose
5.1 When the corresponding committed effective dose equivalent 1g> or committed device (tissue) dose equivalent H generated by the intake dose is known, the calculation can be carried out by any of the following two methods (A or B): 5.1.1 Method A
H.ee($v)-
H...T(S)=
Wu Zhong(AL1)
5.1.2 Method A
Where (DCF),,E-
(DCF>s.--
The random annual acquisition limit value of the nuclear disorder, Bq; The deterministic annual chain entry limit value of the nuclear event, g.X0.05
Ha-=IX(IXCFr(Sv)
（9）
Hu.T=I×(ICF)a.tSv) .
(12)
Intake dose - dose conversion factor, equal to the corresponding cumulative effective dose equivalent generated after the intake of unit activity of radioactive nuclides, S/Bq +
Intake dose conversion factor, equal to the cumulative organ (or tissue) dose equivalent generated after the intake of unit activity of radioactive nuclides, Sv/By.
Example of low calculation of internal radiation dose is Appendix B.5.2. After the internal radiation dose is obtained, the internal radiation dose can be evaluated according to the provisions of 2.1 or 2.2. 5.3 Sometimes, for purposes other than radiation protection, it may be necessary to estimate the cumulative effective dose equivalent H,e or the cumulative organ (or tissue) dose equivalent Hl,1 of radioactive nuclides after intake (years (not necessarily 5 years). In this case, it can be used to calculate C.The method introduced in the above is used to make an approximate estimate based on the committed dose obtained. 624
A1 intake
GB/T16148--1995
Appendix A
(Supplement)
The amount of radionuclides that escape into the human body. The entry routes include inhalation, ingestion and through wounds or intact skin. A2 uptake
The amount of radionuclides that enter the body's extracorporeal fluids after entering the body. A3 retention
The amount of effective radionuclides that remain in organs, tissues or the whole body for a certain period of time after ingestion. The nuclides that are taken up by body fluids are called systemic nuclides. The sum of the systemic retention and the retention in the respiratory and gastrointestinal tracts is called the systemic retention. A4 Punitian The amount of radionuclides deposited in the ingested organ after being taken into the body, for example, the radionuclides deposited in the gastrointestinal tract after an acute inhalation. A5 D class cumpound Compounds with a half-clearance period of less than 10 days in the lungs. A6 W class compound Welass compound Compounds with a half-clearance period of 10 to 100 days in the lungs. A7 Y class compound Compounds with a half-clearance period of more than 10 days in the lungs. A8 Biological compartment Biassy compartment A physical structure composed of an organ or tissue, or a particular bacterial population, in which the material in the compartment is assumed to be instantly mixed with the original material in the compartment. Ag intake retention function (IRF>intake retention function Under single intake, the retention of a nuclide in the whole body, an organ or a tissue accounts for the fraction of the intake amount that changes with the time after intake.
A10 intake excretion function (IEF) intake excretion function Under single intake, the fraction of the nuclide that is excreted from the body through urine, feces, etc. accounts for the fraction of the intake amount that changes with the time after intake.
A11 activity median aerodynamic diameter (AMADactivitymrdlian aerodynaniediameter A ball with a density of 1 g/m\ has the same settling velocity in the air as a particle whose activity is the median of all aerosol particles. The diameter of this ball is the median aerodynamic diameter of the aerosol particles. A12 Annual intake limit (1.1) When a person (represented by a reference person) ingests only one radioactive nuclide, the resulting dose reaches the relevant annual dose equivalent limit set by the country. The activity of the radionuclide ingested under this condition is called the annual intake limit. A13 Accumulated organ (or tissue) dose equivalent (Hs.r> rewntrilulvrkasiorlissuerdobeenuivalent) A certain radioactive nuclide is 50% of the body's internal dose after being ingested. The cumulative dose equivalent averaged over the whole organ (or tissue) produced in a year.
A14 committed effective dose equivalent (Hra.r) committed effectivedauseequivalentHu.. - Zw.f...
+++(Al )
The risk weighting factor of the organ T, which is equal to the ratio of the actual risk caused by the exposure of the tissue to the total risk caused by the exposure of the whole body. Appendix B
Example of estimation and evaluation of exposure dose and internal radiation dose (reference)
Through conventional whole body counters, it was found that the bodies of two personnel A and B were contaminated with 5Cs and \C, and their activities were respectively:
msCs52Bqs
a192Bm
wcs133Bq:
ECo48Bq
Based on recollection and relevant records, it is speculated that the accident occurred in an explosion (inhalation) incident on November 15, 2011. The whole body counter test was conducted on October 15, 2011, and the time from inhalation to the test was 365 days. According to the classification of publication ICP30, the compounds containing 1\Cs they operated belonged to Class L, and the compounds containing \Co belonged to Class W. It was found that the corresponding effective annual intake limits for inhalation of the above-mentioned Class ID 1\Cs and Class W\C were both equal to 6×10Bg. Reference [1] found that the whole body intake retention values of Ce and Co (W) after a single inhalation of 365 days were 5.93×10 and 1.30×10\, respectively (see pages B and 212). The following calculations and evaluations can be performed retrospectively: Notes; 1) Reference text missing [17: ET Lessard, Fu Yika et al., "Estimation of the amount of oral administration of tooth decay for burial of sheep", World Book Publishing Co., Ltd., 19882. According to the standard formula (7), their intake can be estimated as follows: 5.93x10--878 Bu(15Ce)
192 Hul
14 8D0 Bq(Co)
Z:1,=5.93×10
48 H3ru
=3 240 Hg(1(s)
3 700 ByrdCo)
b: Internal radiation agent estimation: According to the standard formula (9), the effective dose equivalent produced by the above-mentioned intake can be obtained as follows: + 14 800(-Co)×0.05=1.3×10 *5v878
6×109
L6×106
Internal radiation intake barrier evaluation:
GB/I 16148-1995
(\C)×0.03=4.95×10-Sv
Use the formula (-) in 2.4 to evaluate the intake, (C)+ 4R0 (n0)=2.61 11≤1
6×105
6×106
+700.cmco)-9.9xt0:s1
6×105
6×106
It can be seen that whether it is based on the above dose-based evaluation or the graded intake evaluation, the mixed internal exposure of \Cs and inCu received by workers A and B in this accident is relatively light. Example 2:
A Class 1 inhalation accident of argon occurs. From the following, the occurrence of the accident was predicted, so urine samples were collected immediately. In order to improve the statistical difference, it is more advantageous to measure the cumulative urine group. According to the average concentration of argon in urine measured, the reference person's daily urine output is assumed to be 1.1 liters, and the content of argon in urine samples at different times after inhalation can be calculated. Then, using the non-standard formula (8) in the text, the best estimate of the intake can be obtained, see Table H1. Table B1: Based on the measured value of uranium in urine, the estimated value of uranium content in urine is estimated to be 0. The estimated value of uranium content in urine samples in Table B1 is obtained from the quick reference table (page B-163) in the literature [1]. The concentration of urinary tract urine can be calculated as follows:
First, calculate the concentration of urine sample A in the first time, AA = r x μr; x 1.4 L/d
Where: 2,
The average concentration of the first urine sample, Bg/1-;
-The difference between the time t of the first sampling and the time of the first sampling, that is, Ar;=t;-t;-1(1.4 1./d is the average urine output per day A - 24: + 44. + 41,
Then use formula (5) to calculate the best estimate of each person's concentration. (B2)
Class person household
CB/T 16148
Table H2 Examples of IRF values for acute ingestion
RF in compartment
Household water, ingestion, ALI=2.35E+C
1. 22K-0!
5. 32F 07
Co: Cannibal AI.1=2 00E 1 07R:1
7.1IE- 32
3- 54F5-02
B-BOE-03
5-95E-33
(m,W suck,ALI-- 5. 4SE+URBA
1-117E·02
F-66E-0!
1-63E-01
1-23E-01
5-77F-02||t t||1.16F-112
", inhalation, ALI8.47E+CB
2-13E-07
1,2F-01
--43F-01
1. EnE c1
1. 37E-C1
1.44F: r:1
*Sr cannibalism+A1.I-1.0GF 1 r6Pn
1. 58E-01
9, 9GF-G2
6. 04E c2
2-44L-02
3. 8nF-112
\SD inhalation LI=7.00E0513
7. 9?H-02
5. 80上-04
2. 96F-02
5. 11E n3
3. 83F-115
3-49stop-0.8
1-25:-C2
2. 52F-04
7-21E:-05
.14H:-06
2:59F-02
2-26F-03
6. 86F-15
1.77 on-05
5-17F-04
5- 43F-05
1- 99F-05
1. 61F-G5
5. 20L-03
3. 4 on F C4
7. 15F-03
2- R7F-13
R.57F-102
2. 15r-5.:
IRF in the trap
7. 81F-02
Gi.681:-02
sT, into,AT.1-1. 0nF+5Lq
2.13±-C1
e-1,D-type absorption,AL1=1.8SF16R
1-20E-01
L- 16F-02
2-74E-01
1-25F-01
1.A1.1-33E+06L4
1-aE-03
1-B3K-02
SCa入.AIL.3.5FE+GBq
20ti,
3G5- C
3.48W-0三
9.2-IE-02
C,D-class inhalation, A11-5.5IE+061g
ti.22F-111
.6F: 4
8. S6F-n2 | | tt | 04F-G:1
[. a8F-14
6. 25E-C#
1-24E-G7
1-19F 03
8. 76E 04
1. 16F-04
1. 665-37
2. FGE-0?
1-27F-U3
7. 1G:-CR
2. 41F-0J
.54E-03
R. tSF-04
3. 00E 04
Yanrendian
Attached room's IRE
LT,D Shuang inhalation AI.I5.UEIU34
7. 57E C2
1.68 Shang-01
5-06F-n2
1-17:-02
1. 15F: 02
UW inhalation,AI.T--2. 52E Iq
14,500-01
1. 02E-u1
4, 18F-f12
1-17L-01
4-81E-02
1. 59E-02
--14E-02
SAT,Y美sorbAL=1.51K-ORR
2- 13F-01
1. 48F-11
1. 45F-51
--C3F-01
5. BSE 01
1-50E-01
RL:, cannibalism, AT.TY, 5SE+CGBg
7. 11F-01
1. 18F-GS
1. 141:-cs
Pu,W class inhalation, AT.T-2.03E+C2g
1: 45E-u1
3-42-02
2. 09F:13
GB/T 16148—1995
Continued Table 132
Spotted
24 hours
1, 11F-114
5- 15F:-06
4. :3F-02
2-69E-03
2. 43H-04
1.29E-115
1. 3-E-04
3.271-0 yuan
2. 00F-34
2. 51E 05 | 22F-01
1-03E-37
3. 64F-02
9- 87E5-01
. 34F-04
1. 21 E5-04
Pu. Cannibal,AT.T-2. 43E-0514
2Am, Cannibal,AT.1 5. WE-4Eq
7. 14E-ct
5. 74F-u2
4. 47F-14
\Am.W Inhalation, AT.I2.0E+02Bg
211F-01
.SUE-C1
1-45F:01
1-32F-01
--36F-01
--5E01
.GSF-01
24 small
7.8.9F-16
1- 55E-35
2-67E-00
f. 09F r.7
7. 73F-t:2
S-312-07
Y-12E-08
2-84F-06
1-5715-08
2. HGE- 51
2.0715-0R
8- PK-C5
C1Estimation method
GB/T 16148—1995
Appendix C
Example of estimation of cumulative internal exposure dose
【Examination】
In the field of radiation protection, the person who evaluates internal exposure usually estimates the accumulated dose within 50 years (specifically called the accumulated dose basis). However, sometimes, for reasons other than radiation quality protection, it is necessary to estimate the cumulative dose equivalent produced within 1 year (not less than 31 years) after the radionuclides enter the human body. In general, in order to calculate this type of dose,It is best to adopt a method of specific calculation for each problem. However, since this method of solving each problem one by one is generally time-consuming and not easy to be widely used, necessary simplifications are made within the scope of this standard. Within the scope of this standard, the cumulative dose equivalent in a year can be calculated using the calculation results of the cumulative dose equivalent. HR - Hro.EX f
Ifr = f × J
In this case, the cumulative effective dose equivalent generated in the previous year + H.1-the cumulative organ (tissue) dose equivalent generated in the year: HE-and the corresponding cumulative organ (tissue) dose equivalent to be accumulated: Hsn.
The positive coefficient
can be determined by the following three situations respectively. When the values of 20T:a or IRIF are greater than zero before the year, if they are less than 1×13- (Figure C1), then f=1
Here, T is the physical half-life of the nucleus. IRF is the systemic uptake hysteresis function of the nucleus by the relevant excretion pathway (excretion is not applicable).
When the IRF value approaches zero at some time between 1 year and 50 years (Figure C2), then b.
a. IRFw is zero before t-1
GE/16148-1995
b, IRFw is zero before 50 years
S,-JIRFwnde
S, =JIRFmdz
IRFm tends to decrease after 50 years
RFwgrlt
2 years:
IKFwl line is the area between (i.e. RFid) and Fdr
When the TRF interval value reaches zero after 50 years (doctor (:3), then: the area between RFlir line and (i.e. TRFw) [\IRFwgle)
1RF The area between 56 and 66 is used (
Center 2 Estimation Example
Example 1: It is required to estimate the cumulative effective dose equivalent and cumulative thyroid dose equivalent after inhalation of 2×1 heart flash\1-year. H
"\1 T1, 0.C221 years, in this question {=1 year so it meets the requirements of:, so the coefficient of refinement 1, =1, from reference [2]\, the accumulated effective dose equivalent after inhalation of 11] is 8.3×10mSv: the accumulated thyroid dose equivalent of the hearing loss is 2. ×10 rnSv
, 1) Reference [27, Supplencn:o:ICRPPublicat:cn 20.Limitxfer Intkrxif Tarlion:rlile hy Wmrk-.195] can be calculated according to formulas (C1) and (C2) to obtain the cumulative effective dose equivalent after inhalation of 2×10 The cumulative effective dose equivalent (HE) produced within three days after inhalation of 4×10°11\(s(1) type) is required to be estimated. From the 1RF curve of 1C (see reference 1]B.~1:1 page), it is basically practical in a 2050-day period [: trend -F], the systemic retention function required for inhalation of 10 s after ingestion is shown in Table C1. 631
micro-tablet large number
total number after ingestion,
approximately number of days after ingestion
number of days after ingestion d
CB/T16148-1995
systemic retention function after inhalation of 10 s after ingestion Table C1
3.35×10-
1. 8X 10 1
9. 94× 1m-
Art CKOG
1. 7- ×10-*
From the above curve, we can calculate the total area burned at different times. The following approximate numerical integral formula can be used to find the face recognition:
+[+++i+f..+
\rz)de-
is the number of equal segments of the integral interval (one);
is the IRFwu value at the corresponding equal segment point.
Sfho h
In reference [1], the time interval is divided into segments in the form of 10. Therefore, for simplicity, the integral value can be calculated segment by segment and then added.
Therefore, the integrals required in this example are as follows: J, IRFwudr=JoIRFwdr+J, IRFwndr+I, IRFwrd: IJoIRFwnds+,622+0. 6380. 636+0.63510 63910. 6310.629+0. 628+0.525+where IRFwed
0. 62]= 0. 6419
0.5485.157
0. 325J-37. 09
where 85 52
so:J. IRFgdz=0. 649 1 5. 157 -37. 09+42. 16=85. 06Similarly, we can get
JeIRFwndtJIRPaede-+JIRFwndr+JoouIRFwsde=[0. 649-5. 157 +37, 09)—49. 34+0. 498=92.73
So
IRFwadr
CB/T 16148
From the text of Shun.21, we can find that the cumulative effective dose produced by inhaling 13Cs is equivalent to 83×11-mSv/F1. So, using formula (C3), we can calculate that the maximum cumulative effective dose produced by inhaling 4×10° 13 l4(cs within 400 days is: II um,E 4 × 1F Hg × 8. 33 × 10-t ra.Sv/Fkl × n. 91730.5mSv
Example 3: It is required to estimate the cumulative effective dose produced by inhaling 455 BgY-type\U tablets for three years (a 000 The cumulative effective dose produced by inhaling 450 Y-type “disease” within three years is equivalent to the cumulative effective dose produced by inhaling 450 Y-type “disease”. The corresponding IRFm (see page B-451) function can be found in reference 1. It can be seen that it is far from zero until 50 years (18250 days). Therefore, it is estimated according to formula (C1). Using the same method as in Example 1, it can be calculated that: \ ++
- 0.642 - 2.11 — 12.8 81.1 * 96.64 iRanda -+ F+
= 96.64 + 116.6 + 33 = 236.12 Therefore,
IRFwudl
Therefore, the cumulative effective dose equivalent produced by inhaling 450 Y-type “disease” within three years after death is: (the effective dose equivalent of inhaling Y-type “disease” is 0.025nSv/By>H:.E= 45 [3qX 0.025 mSv/HaX 0.41=4-6a nSv
C3 Discussion on Several Related Issues
C3.1 Limitation on Estimation Time
Since the data provided by ICRF Report No. 1 for occupational radiation protection are all based on the accumulated dose generated within 50 years, and the distribution of radioactive nuclides in various parts of the body after entering the human body will change with time. Therefore, in principle, the approximate calculation method introduced in this paper is acceptable as long as the early stage when the residual distribution of nuclides is still quite unstable can be obtained, that is, under the premise of applying appropriate restrictions. The following four situations can be considered for the limitation:
For any nuclide and any intake route (inhalation category), it is obvious that as long as the intake is longer than the physical half-life of the nuclide (such as t>20), the estimation result is completely acceptable. Fortunately, most medical agents can easily meet this requirement! b. For human beings or ingestion, the best exposure is more than one week, and for inhalation, the best exposure is more than 3 months; d. For inhalation, the best exposure is more than 3 years.2. Regarding the estimation of uterine (tissue) cumulative dose, this standard will use the total body intake retention function to simultaneously estimate the cumulative effective dose equivalent and the cumulative organ (tissue) dose equivalent. This is because the reference document only provides organ retention functions for the thyroid gland and lungs, and only provides systemic and whole body retention functions for the others. In addition, the source organ calculation is not limited to the irradiated organ itself, so it will make the problem more complicated. Therefore, we recommend that the whole body intake retention function be used as the basis for calculation. As long as certain control requirements are met for the same, this treatment can simplify the problem.
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