EN
OSGI-P Reference (exemplary) and control sources: Sealed radionuclide sources of photon radiation reference / OSGI-P set
Application: OSGI are used as working standards for verification and calibration of photon radiation measuring instruments, certification of measurement methods and control of the correctness of photon radiation measurements.
In particular, the set is intended for testing and calibrating precision instruments, spectrometers and radiometers, ionization chambers and scintillation counters. A special area of application of reference spectrometric sources is testing and calibrating spectrometers used in environmental studies.
Description: The source is a disk made of organic glass with a diameter of 25 mm and a thickness of 3 mm. The ceramic active part (BeO) with the embedded radionuclide preparation is placed in the center of the body, sealed with epoxy resin. The diameter of the active part is 2 mm.
Radionuclide |
Half life | Main energy 1) , keV | The yield of gamma quanta for decay |
Activity of radionuclide in source 2) , kBq |
Radionuclide impurities 3) , %, no more than |
Photon radiation transmittance coefficients 4) |
| Na-22 | 950.57±0.23 | 1274.54 | 0.99940±0.00014 | 5 – 1000 | 0.01 | 0.988 |
| Ti-44 | 21915±400 | 67,884 | 0.930±0.020 | 5 – 100 | 0,001 | 0.963 |
| Mn-54 | 312.29±0.26 | 834,848 | 0.999746±0.000011 | 5 – 1000 | 0.15 | 0.985 |
| Co-57 | 271.80±0.05 | 122,061 | 0.8551±0.0006 | 5 – 3700 | 0.15 | 0.967 |
| Co-60 | 1925.23±0.27 | 1332,50 | 0.999826±0.000006 | 5 – 3700 | 0,1 | 0.988 |
| Zn-65 | 243.86±0.20 | 1115,55 | 0.5060±0.0022 | 5 – 1000 | 0.2 | 0.987 |
| Y-88 | 106.625±0.024 | 1836,066 | 0.9938±0.0003 | 5 – 1000 | 0,1 | 0.991 |
| Cd-109 | 461.4±1.2 | 88,034 | 0.03626±0.00020 | 5 – 1000 | 0,001 | 0.965 |
| Sn-113 | 115.09±0.04 | 391.71 | 0.6494±0.0017 | 5 – 100 | 0.01 | 0.978 |
| Ba-133 | 3848.7±1.2 | 356,014 | 0.6205±0.0019 | 5 – 3700 | 0,001 | 0.977 |
| Cs-134 | 753.5±1.0 | 604.7 | 0.97650±0.00018 | 5 – 300 | 0.01 | 0.982 |
| Cs-137 | 10990±40 | 661,66 | 0.8499±0.0020 | 5 – 1000 | 0.05 | 0.983 |
| Ce-139 | 137.642±0.020 | 165.86 | 0.7990±0.0004 | 5 – 1000 | 0,1 | 0.969 |
| Eu-152 | 4941±7 | 1408,006 | 0.2085±0.0009 | 5 – 1000 | 0.15 | 0.988 |
| Gd-153 | 240.4±1 | 97.43 | 0.290 | 5 – 500 | 0.2 | 0.965 |
| Bi-207 | 11800±300 | 569.7 | 0.9776±0.0003 | 5 – 100 | 0.2 | 0.982 |
| Pb-210 | 81083±80 | 46.54 | 0.0425±0.0004 | 5 – 200 | - | 0.960 |
| Th-228 | 698.6±0.23 | 2614 | 0.99754±4 | 5 – 50 | 0.2 | 0.998 |
| Am-241 | 157850±230 | 59,537 | 0.3578±0.0009 | 5 – 370 | 0.05 | 0.962 |
| Am-243 | 2692000±8000 | 74.67 | 0.672 | 5 – 50 | ˂5 | 0.964 |
1) Data source: Nuclear and Atomic Decay Data, version 1-98. Bé M. – M et al., 1998, BNM-CEA-LPRI, Saclay, France
2) The nominal value of the radionuclide activity in the source within the specified limits is set by the consumer when ordering the source. The deviation of the activity from the nominal value should not exceed -10% +30%
3) The ratio of the total activity of impurity radionuclides to the activity of the main radionuclide in the source
4) Transmission coefficients of photon radiation in the housing of the OSGI-P type source
- The source is always used in only one version - the working (emitting) surface is located on the side opposite the marking.
- Experimental data and interpolation/extrapolation data were used to determine the transmittance coefficients.
- Transmission coefficients for other energy lines are calculated by interpolation.
ISO Classification: C34343
Confidence limits of measurement result error at confidence probability p=0.95: 3%
Designated service life and inter-verification interval of sources
