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Basic data
| Standard ID | WS/T 614-2018 (WS/T614-2018) |
| Description (Translated English) | Rapid analysis method of radionuclides by gamma spectrometry under emergency |
| Sector / Industry | Health Industry Standard (Recommended) |
| Classification of Chinese Standard | C57 |
| Word Count Estimation | 19,171 |
| Date of Issue | 2018-06-15 |
| Date of Implementation | 2018-12-01 |
| Regulation (derived from) | National Health Newsletter (2018) No.12 |
| Issuing agency(ies) | National Health Commission |
WS/T 614-2018: Rapid analysis method of radionuclides by gamma spectrometry under emergency
---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
Rapid analysis method of radionuclides by gamma spectrometry under emergency
ICS 13.280
C 57
WS
People's Republic of China Health Industry Standard
Rapid Analysis of γ Spectra of Radionuclides in Emergency Situation
method
2018 - 06 - 15 released
2018 - 12 - 01 Implementation
National Health and Wellness Committee of the People's Republic of China
Content
Foreword... II
1 Scope... 1
2 Normative references... 1
3 Terms and Definitions... 1
4 Instruments and Equipment... 1
5 Sample Collection... 2
6 Sample Pretreatment... 3
The scale of the gamma ray spectrometer is ... 5
8 Sample Measurements... 5
9 Quality Control... 5
10 Results Report... 6
Appendix A (informative) Radionuclides that may be involved in the emergency response... 7
Appendix B (informative) Radionuclides that may be released from nuclear power plants... 13
Appendix C (informative) The measurement time of samples in emergency and the minimum detectable activity concentration of typical radionuclides... 14
references... 15
Foreword
This standard was drafted in accordance with the rules given in GB/T 1.1-2009.
This standard was proposed by the National Health Standards Committee Radiological Health Standards Committee.
This standard was drafted. Radiation Protection and Nuclear Safety Medical Institute of China Center for Disease Control and Prevention, Tsinghua University, Academy of Military Medical Sciences
Institute of Radiation Medicine and Radiation Medicine, Institute of Radiation Medicine, Shandong Academy of Medical Sciences, Xinjiang Uygur Autonomous Region Center for Disease Control and Prevention.
The main drafters of this standard. Tuo Fei, Zhou Qiang, Hou Changsong, Zhao Lancai, Zeng Zhi, Yang Baolu, Yang Guoshan, Li Zeshu, Zhu Maoxiang, Yuan
Long, Deng Daping, Wang Yuwen, Zhang Jing, Xu Jiaang, Li Wenhong.
Rapid analysis method of gamma energy spectrum of radionuclide in emergency situation
1 Scope
This standard specifies the rapid analysis method for the sample radionuclide gamma spectrometer in emergency situations.
This standard is applicable to emergency conditions, emergencies or qualitative identification of gamma radionuclides in original samples and quantification in a short time.
The gamma radionuclide activity concentration in the sample was analyzed.
2 Normative references
The following documents are indispensable for the application of this document. For dated references, only the dated version applies to this document.
For undated references, the latest edition (including all amendments) applies to this document.
GB/T 5750.2 Standard Test Method for Drinking Water Standards Collection and Preservation of Water Samples
GB/T 11713 General method for high purity 锗 γ spectroscopy
WS/T 184 γ-ray spectrum analysis method for radionuclide in air
3 Terms and definitions
The following terms and definitions apply to this document.
3.1
Emergency emergency
Rapid action is needed to mitigate unconventional conditions that pose harm or adverse consequences for human health and safety, quality of life, property or the environment.
3.2
Emergency monitoring
Radiation monitoring for the detection or identification of radioactive contamination or radiation levels of persons and places in an emergency situation.
4 Instruments and equipment
4.1 Weighing equipment
Analyze the balance, or an electronic scale that can be accurate to 0.1 g.
4.2 Sample box
The sample box used for the measurement shall be of the same material, size and capacity as the sample box used for the efficiency scale. Cylindrical type is preferred in emergency situations
Sample box or Marlin Cup sample box that matches the size of the detector.
4.3 Sample crushing and shaking device
The sample pulverizing and shaking device includes a commonly used chopping and pulverizing shaking device such as a mortar, a cutter, and a food processing machine.
4.4 High Purity Germanium (HPGe) Gamma Spectrometer Measurement and Analysis System
High purity germanium (HPGe) gamma spectrometer measurement and analysis system, energy response should be covered between 40 keV ~ 2 000 keV, the specific available energy
The range of quantities is determined by the energy scale and the efficiency scale. Further use and specific configuration of high purity germanium (HPGe) gamma spectrometer measurement and analysis system
See standard GB/T 11713.
4.5 Standard source
The standard source refers to a standard sample of known radionuclide activity concentrations. Includes energy scale standard source and efficiency scale standard source. It fired
The gamma ray energy should cover the energy range of the nuclides in the emergency situation. It is known that the activity concentration of the radionuclide should be traced back to the national benchmark.
See Appendix A for radionuclides that may be involved in the emergency response. See Appendix B for radionuclides that may be released from nuclear power plants.
4.6 Passive Efficiency Calibration Software
The passive efficiency calibration software is software that obtains the relationship between energy and efficiency through computer simulation. Passive efficiency calibration software
Contains unique characterization parameters for the detectors used and can be used in conjunction with spectral analysis software. Use the actual standard when using passive efficiency calibration software
The quasi source is verified.
5 sample collection
5.1 Sample Collection Principle
5.1.1 Sampling personnel should be personally protected from radioactive contamination.
5.1.2 Monitoring of sampling sites in emergency situations should take into account local meteorological conditions, at the highest concentration of predicted pollution, dominant downwind direction and population
Dense areas are properly encrypted.
5.1.3 Before the sample is collected, the gamma radiation level around the collection site should be patrolled and recorded, and surface contamination detection can be performed if necessary.
To determine the extent and extent of radioactive contamination, focus on samples collected in areas with high levels of pollution.
5.1.4 The collected samples should be double-labeled and numbered, and the sampler, sampling date and time, sampling amount and sampling location should be recorded in detail.
Information such as latitude coordinates).
5.1.5 Samples of food and drinking water collected should be representative. Combine the sampling season with the local dietary structure, giving priority to open-air growth
food.
5.1.6 The methods and tools used for sample collection shall not cause contamination of the sample to be tested and result in loss of the nuclide to be tested. Sample collection container
If reuse is required, care should be taken to avoid cross-contamination.
5.1.7 During the emergency period, in principle, radioactive monitoring of food or drinking water should be carried out daily. The sampling amount of food or drinking water should generally be quite small.
Fresh weight 5 kg or 5 L.
5.2 Air
The air sample collects the airborne particulate sample in the air on the filter by means of an air sampling pump, and collects the gaseous radioactive iodine in the air.
Use adsorption cartridges or specially treated chemical absorbents. For detailed collection methods, see WS/T 184.
5.3 Precipitation
During the emergency period, rain or snow water samples should be collected in a timely manner when rainfall or snowfall is expected or has occurred. Precipitation collection device should be placed around
A flat, open floor with a radius of 30 m without trees and buildings, and a collection device 1 m above the ground. In the case of heavy rain,
When the initial rainfall is collected. The collected snow samples should be moved indoors to allow them to naturally melt.
5.4 Soil
Collect surface soils most likely to be contaminated by radionuclides, with a depth of 0 cm to 5 cm; the location of the collection is preferably flat,
Open ground; sampling volume is about 2 kg ~ 3 kg; generally in the range of 10 m × 10 m, the sample is collected by the five-point method.
5.5 pasture
When collecting forage samples, cut them from the exposed roots to avoid soil contamination.
5.6 Food
5.6.1 Milk
Milk samples should be sampled directly at the milk station, farmer or animal and recorded for animal feed.
5.6.2 Vegetables and fruits
In the stage of radioactive sedimentation, vegetables and fruits grown in the open field should be collected. When sampling, take care to avoid soil contamination.
5.6.3 Cereals and potatoes
In the harvest season, the grain and potatoes of the planting area are collected directly. If it has been packed into a bag, it can be taken into the bag by a sampler commonly used in the grain depot.
kind.
5.6.4 Meat
Meat samples are best collected at a slaughterhouse in a local farm and record animal feed information.
5.6.5 Seafood
Seafood samples are collected directly from offshore farms or purchased from fishing companies to identify seafood in the fishing area.
Record feed information.
5.7 Water
Includes drinking water, surface water and sea water. The collection of drinking water in accordance with the provisions of GB/T 5750.2. Surface water and seawater sampling
Refer to the collection of GB/T 5750.2 source water.
5.8 Other samples
The collection of other samples such as debris, rubble, waste residue, building materials, etc., combined with the actual situation of the site under emergency conditions, for the samples to be sent,
You can register by submitting the inspection record.
6 sample pretreatment
6.1 Pretreatment principles
The pretreatment of the sample in an emergency situation should be based on the principle of rapid and scientific, and the sample is measured after simple treatment. Geometric strip for its sample measurement
Parts should be as consistent as possible with the efficiency scale standard source. According to the monitoring of the sampling is to evaluate the degree of radioactive contamination, or to evaluate the way of eating
Different purposes such as the dose caused by the diameter, combined with local eating habits, choose to clean or not clean the food sample, peel or not peel, etc.
Indicated in the report.
6.2 Air
The filter material was taken out from the sampler, folded flat in the sample box, and measured directly after compaction, fixed capping and sealing.
6.3 Soil
After removing foreign matter such as stones and weeds, directly fill the sample box and measure about 100 g of soil sample for measuring the dry/wet ratio.
6.4 Pasture
Remove the sand, dirt and roots, cut them into small pieces of 1 cm ~ 2 cm, and fill them with a sample box.
6.5 Food
6.5.1 Milk
Milk samples can be measured directly.
6.5.2 Vegetables
Vegetable samples remove inedible roots, stems, leaves and decayed parts, and the samples are processed to a geometry of less than 1 cm3 and filled with samples
Box measurement.
6.5.3 Fruit
Fruit samples should be processed to a geometry of less than 1 cm3 and filled with sample boxes for measurement.
6.5.4 Cereals
After the cereal samples are removed from sand and dust, they are directly filled in the sample box for measurement.
6.5.5 Potato
After the potato sample is removed from the sediment and the decayed part, the sample is processed into a geometric size of less than 1 cm3 by cutting and pulverizing.
Full sample box measurement.
6.5.6 Meat and seafood
Take the edible portion, cut it to a geometric size of less than 1 cm3, and fill the sample box to measure.
6.6 Water
Add 10 mL of 11 mol/L hydrochloric acid or nitric acid per liter of sample to acidify and directly fill the sample box.
6.7 Other samples
Samples such as residue, rubble, waste residue, building materials, food desiccant, etc., crushed, ground, sieved through a 50-mesh sieve, and loaded for measurement. other
Samples, including environmental sedimentation ash, wiping samples, consumer goods, clothing, and special items (such as gems, jade, wood, crafts, watches)
Etc., etc., if there is no special requirement, no destructive pretreatment is required, and it can be directly placed in the measuring chamber after simple anti-pollution sealing.
measuring.
7 gamma spectrometer scale
7.1 Energy scale
Place the energy calibration standard source at the appropriate position of the detector, and use the spectrum analysis software to obtain the peak of the omnipotent peak to determine the peak position and energy.
Relationship, the source of the energy scale standard in an emergency situation can be determined by means of an efficiency scale standard source of known species, or by lead chamber natural background nuclide
Fast energy check.
7.2 Efficiency scale
7.2.1 Active efficiency scale
The active efficiency calibration method is implemented in accordance with GB/T 11713, and should be completed and stored in advance under normal conditions. After rapid verification in emergency situations.
Called directly.
7.2.2 Passive Efficiency Scale
Passive efficiency calibration software or Monte Carlo simulation based methods can be used for rapid simulation of efficiency in emergency situations. Passive effect
Rate calibration software requires active efficiency calibration and passive efficiency calibration for samples of several common media (such as water, soil, etc.).
The comparison of values can be applied when the maximum relative deviation of the energy segment efficiency values is known to be no more than 15%.
8 sample measurement
8.1 Measurement principles
Qualitative identification and quantitative measurements can be performed as needed in emergency situations. For qualitative identification, the sample pretreatment process can be further simplified.
After the energy calibration is completed, the species of the nuclide can be quickly reported as long as the nuclide to be detected is accurately identified.
See Appendix C for the measurement time in an emergency and the minimum detectable activity concentration of a typical radionuclide in a sample. Specific measurement time
The adjustment can be made according to the detection efficiency of the gamma spectrometer, the background, the activity of the radionuclide in the sample, and the emergency work needs.
8.2 Measurement methods
8.2.1 To prevent contamination of the detector, the sample to be tested is wrapped in a polyethylene bag.
8.2.2 Place the sample to be tested on the detector for measurement. The position of the sample to be tested should be consistent with the standard source of the efficiency scale.
8.2.3 Radionuclide identification based on the energy of the omnipotent peak. At the end of the measurement, the energy scale should be verified to ensure reliable identification of the nuclide.
8.2.4 Call the stored detection efficiency value to determine the level of gamma radionuclide in the sample; for irregularly sized sample shapes,
Efficiency simulation is performed in conjunction with passive efficiency calibration software.
8.2.5 The quantitative calculation of radionuclides in the sample and the uncertainty assessment of the results can be found in GB/T 11713.
8.2.6 At the beginning and end of the measurement, the background spectrum of the instrument should be measured to prevent inaccuracies in the measurement results caused by detector contamination.
9 quality control
9.1 Daily maintenance
9.1.1 Instrument verification or calibration test
Relevant equipment used for measurement and analysis (such as high-purity 锗 gamma spectrometer, etc.) must be verified or calibrated by the national legal metrology department and is valid.
Used during the period.
9.1.2 Retest
In order to check the analytical precision of the sample, the sample should be repeatedly measured in time, and the repeated error rate (DER) between the two results should be calculated.
As shown in equation (1).
Original dup
twenty two
c original c dup
AC AC
DER
u AC u AC
...(1)
In the formula.
ACoriginal - The activity concentration of a nuclides in the initial sample, in units of Becker per kilogram (Bq/kg), or Becker per liter (Bq/L),
Or millibeltz per cubic meter (mBq/m3);
ACdup -- The activity concentration of a nuclides in a retest sample, in units of Becker per kilogram (Bq/kg), or Becker per liter (Bq/L).
Or millibeltz per cubic meter (mBq/m3);
Uc(ACoriginal) - The extended uncertainty of a nuclides in the initial sample, in units of Becker per kilogram (Bq/kg), or Becker per liter
(Bq/L), or millibeltz per cubic meter (mBq/m3);
Uc(ACdup) -- The expanded uncertainty of a nuclides in a retest sample, in units of Becker per kilogram (Bq/kg), or Becker per liter
(Bq/L), or millibeltz per cubic meter (mBq/m3).
The value of DER should be less than or equal to 3. If the retest value of the sample is not within this limit, the batch of samples needs to be retested, or when appropriate
Give explanations. For samples with measurement results below the lower detection limit, the retest results should also be consistent.
9.2 Quality control in emergency situations
9.2.1 Instrument check
In an emergency situation, the instrument is calibrated using a standard source before measuring the sample.
9.2.2 Sample retest
In case of emergency, after completing a batch of sample testing, the sample can be repeatedly measured and DER is calculated to determine whether the batch test result is
reliable.
10 Results report
10.1 Report sample analysis results should be clear and concise, with appropriate instructions.
10.2 In addition to the qualitative identification of the units that do not give the reported results, other quantitative reports should use the International System of Units (SI) units and symbols, one
Some standard units are recommended as follows. Air. mBq/m3, water and milk, etc.. Bq/L, soil and pasture. Bq/kg (dry or fresh weight),
Food. Bq/kg (dry weight or fresh weight).
10.3 For quantitative analysis, the measurement results of the nuclide and its extended uncertainty should be given, and the confidence of the extended uncertainty should be noted. Undefined expansion
The calibration generally retains 1 significant digit. When the first position of the extended uncertainty is less than “3”, 2 significant digits can be reserved; the measurement result is valid.
The number should be determined according to the principle of the last digit of the measurement result and the last alignment of the uncertainty.
10.4 When measuring at low level of activity, the lower limit of detection should be given when the lower limit of detection is exceeded, and the measurement conditions should be appropriately indicated, such as the spectrometer system master
Performance, measurement time, use of characteristic peaks, measurement geometry, etc.
Appendix A
(informative appendix)
Radionuclides that may be involved in emergency response
The radionuclides that may be involved in the emergency response are shown in Table A.1.
Table A.1 Radionuclides that may be involved in emergency response
Nuclide
Gamma ray energy
keV
Gamma ray branching ratio
half life
Ac-227 100 3.17×10-4 7.96×103
Ac-227 83.96 2.21×10-4 7.96×103
Ag-110m 657.75 9.47×10-1 2.50×102
Ag-110m 884.67 7.29×10-1 2.50×102
Am-241 59.54 3.63×10-1 1.58×105
Am-242m 49.3 1.90×10-3 5.55×104
Am-243 74.67 6.60×10-1 2.70×106
Au-198 411.80 9.55×10-1 2.70×100
Au-198 70.82 1.38×10-2 2.70×100
Ba-133 30.97 6.29×10-1 3.91×103
Ba-133 355.86 6.23×10-1 3.91×103
Ba-137m 661.62 9.00×10-1 1.77×10-3
Ba-137m 32.19 3.82×10-2 1.77×10-3
Ba-140 537.38 1.99×10-1 1.28×101
Ba-140 29.96 1.43×10-1 1.28×101
Bi-207 569.67 9.80×10-1 1.39×104
Bi-207 1063.62 7.70×10-1 1.39×104
Cd-109 24.95 1.43×10-1 4.53×102
Cd-113m 263.7 6.00×10-5 5.33×103
Cd-113m 23.17 6.00×10-5 5.33×103
Ce-141 145.45 4.80×10-1 3.24×101
Ce-141 36.03 8.88×10-2 3.24×101
Ce-143 293.3 4.34×10-1 1.40×100
Ce-143 36.03 3.23×10-1 1.40×100
Ce-144 133.53 1.08×10-1 2.84×102
Ce-144 36.03 4.80×10-2 2.84×102
Cf-252 43.4 1.30×10-4 8.99×102
Cm-242 44.03 3.25×10-4 1.63×102
Cm-243 103.75 2.08×10-1 1.04×104
Cm-244 42.82 2.55×10-4 6.61×103
Table A.1 (continued)
Nuclide
Gamma ray energy
keV
Gamma ray branching ratio
half life
Cm-245 103.76 2.30×10-1 3.11×106
Co-58 810.75 9.95×10-1 7.08×101
Co-58 511 3.00×10-1 7.08×101
Co-60 1332.51 1.00×100 1.93×103
Co-60 1173.23 9.99×10-1 1.93×103
Co-60 2158.7 8.00×10-6 1.93×103
Cr-51 320.07 9.83×10-2 2.77×101
Cs-134 604.66 9.76×10-1 7.53×102
Cs-134 795.76 8.54×10-1 7.53×102
Cs-136 818.5 1.00×100 1.30×101
Cs-136 1048.07 8.00×10-1 1.30×101
Cs-137 661.62 8.46×10-1 1.10×104
Cs-137 32.19 3.70×10-2 1.10×104
Eu-152 40.12 3.00×10-1 4.64×103
Eu-152 121.78 2.92×10-1 4.64×103
Eu-154 123.1 4.05×10-1 3.11×103
Eu-154 1274.8 3.55×10-1 3.11×103
Eu-155 86.45 3.27×10-1 1.81×103
Eu-155 105.31 2.18×10-1 1.81×103
Fe-59 1099.22 5.65×10-1 4.51×101
Fe-59 1291.56 4.32×10-1 4.51×101
Gd-153 41.54 6.00×10-1 2.42×102
Gd-153 40.9 3.20×10-1 2.42×102
Hf-181 482.16 8.60×10-1 4.25×101
Hf-181 133.05 4.30×10-1 4.25×101
Hg-203 279.17 8.15×10-1 4.66×101
Hg-203 72.87 6.40×10-2 4.66×101
Ho-166m 184.41 7.39×10-1 4.38×105
Ho-166m 810.31 5.97×10-1 4.38×105
I-125 27.47 7.30×10-1 6.01×101
I-125 27.2 3.92×10-1 6.01×101
I-129 29.78 3.60×10-1 5.73×109
I-129 29.46 1.90×10-1 5.73×109
I-131 364.48 8.12×10-1 8.04×100
I-131 636.97 7.27×10-2 8.04×100
I-131 284.29 6.06×10-2 8.04×100
I-131 80.18 2.62×10-2 8.04×100
I-131 29.78 2.59×10-2 8.04×100
Table A.1 (continued)
Nuclide
Gamma ray energy
keV
Gamma ray branching ratio
half life
I-132 667.69 9.87×10-1 9.92×10-2
I-132 772.61 7.62×10-1 9.92×10-2
In-114m 24.21 2.00×10-1 4.95×101
In-114m 189.9 1.77×10-1 4.95×101
Ir-192 316.49 8.70×10-1 7.40×101
Ir-192 468.06 5.18×10-1 7.40×101
K-40 1460.75 1.07×10-1 4.68×1011
La-140 1596.2 9.55×10-1 1.68×100
La-140 487.03 4.30×10-1 1.68×100
Mn-54 834.81 1.00×100 3.12×102
Mo-99 140.51 9.09×10-1 2.76×100
Mo-99 739.47 1.30×10-1 2.76×100
Na-22 511 1.80×100 9.50×102
Na-22 1274.54 9.99×10-1 9.50×102
Nb-94 871.1 1.00×100 7.42×106
Nb-94 702.5 1.00×100 7.42×106
Nb-95 765.82 9.90×10-1 3.52×101
Nd-147 91.1 2.83×10-1 1.11×101
Nd-147 38.72 2.30×10-1 1.11×101
Nd-147 531 1.35×10-1 1.11×101
Np-237 86.49 1.31×10-1 7.82×108
Np-237 29.38 9.80×10-2 7.82×108
Np-237 95.87 2.96×10-2 7.82×108
Np-239 103.7 2.40×10-1 2.36×100
Np-239 106.13 2.27×10-1 2.36×100
Pa-234m 1001.03 5.90×10-3 8.13×10-4
Pa-234m 766.6 2.07×10-3 8.13×10-4
Pb-210 46.52 4.00×10-2 7.45×103
Pm-145 37.36 3.86×10-1 6.47×103
Pm-145 36.85 2.11×10-1 6.47×103
Pm-147 121.2 4.00×10-5 9.58×102
Pm-149 285.9 3.10×10-2 2.21×100
Pm-149 859.4 1.00×10-3 2.21×100
Pm-151 340.08 2.24×10-1 1.18×100
Pm-151 40.12 1.66×10-1 1.18×100
Po-210 803 1.10×10-5 1.38×102
Pr-144 696.49 1.49×10-2 1.20×10-2
Pr-144 2185.61 7.70×10-3 1.20×10-2
Table A.1 (continued)
Nuclide
Gamma ray energy
keV
Gamma ray branching ratio
half life
Pu-236 47.6 6.90×10-4 1.04×103
Pu-236 109 1.20×10-4 1.04×103
Pu-238 43.45 3.80×10-4 3.21×104
Pu-238 99.86 7.24×10-5 3.21×104
Pu-239 51.62 2.08×10-4 8.81×106
Pu-239 129.28 6.20×10-5 8.81×106
Pu-240 45.24 4.50×10-4 2.39×106
Pu-240 104.23 7.00×10-5 2.39×106
Pu-241 98.44 2.20×10-5 5.54×103
Pu-241 94.66 1.20×10-5 5.54×103
Pu-241 111 8.40×10-6 5.54×103
Pu-242 44.7 3.60×10-2 1.41×108
Pu-242 103.5 7.80×10-3 1.41×108
Ra-226 185.99 3.28×10-2 5.84×105
Ra-226 83.78 3.10×10-3 5.84×105
Rb-86 1076.63 8.76×10-2 1.86×101
Rh-106 511.8 2.06×10-1 3.46×10-4
Rh-106 621.8 9.81×10-2 3.46×10-4
Ru-103 497.08 8.64×10-1 3.94×101
Ru-103 610.33 5.30×10-2 3.94×101
Sb-124 602.71 9.81×10-1 6.02×101
Sb-124 1691.04 5.00×10-1 6.02×101
Sb-126 695.1 9.97×10-1 1.25×101
Sb-126 666.2 9.97×10-1 1.25×101
Sb-127 685.5 3.57×10-1 3.85×100
Sb-127 473 2.50×10-1 3.85×100
Sc-46 1120.52 1.00×100 8.39×101
Sc-46 889.26 1.00×100 8.39×101
Se-75 264.65 5.86×10-1 1.20×102
Se-75 136 5.60×10-1 1.20×102
Sn-113 391.71 6.42×10-1 1.15×102
Sn-113 24.21 3.90×10-1 1.15×102
Sn-123 1089 6.00×10-3 1.29×102
Sn-123 1032 4.00×10-4 1.29×102
Sn-125 1066.6 9.00×10-2 9.62×100
Sn-125 915.5 4.25×10-2 9.62×100
Sn-126 87.57 3.75×10-1 3.65×107
Sn-126 26.11 1.89×10-1 3.65×107
Table A.1 (continued)
Nuclide
Gamma ray energy
keV
Gamma ray branching ratio
half life
Sr-89 909.2 9.50×10-4 5.05×101
Ta-182 67.75 4.13×10-1 1.15×102
Ta-182 1121.28 3.50×10-1 1.15×102
Tb-160 876.37 3.00×10-1 7.21×101
Tb-160 298.57 2.74×10-1 7.21×101
Tc-99 89.6 6.50×10-6 7.82×107
Te-127 417.9 9.93×10-3 3.90×10-1
Te-127...
...
