RITVERC JSC
RITVERC JSC
10, Kurchatova str., 194223,
St. Petersburg, Russia
Phone: +7 812 297-44-63
Fax: +7 812 297-58-87
Email: info@ritverc.com
Url: www.ritverc.com

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Point Sources

Rectangular point sources Plastik point sources Point gamma-sources

Certificates and documentation

  • NRC Certificate SSDR LA-1491-S-106-S OSGI-RT Refernce Sources EN
  • Pattern approval certificate of measuring instruments ОС.С.38.001.А No 72829 RU

Rectangular point sources

Description

The source is a 2 mm thick plexiglass plate. The ceramic active part with the embedded radionuclide preparation is placed in the center of the body, the sealing is made with epoxy resin. The diameter of the active part is 2 mm, the height is 0.5 mm.

Radionuclide Half-life, days Photon energy, keV Photons per 100 disintegration Activity, kBq * Impurities, % ** Coeffi­cients of the photon radia­tion trans­mis­sion;***
22Na 950.57 ± 0.23 1274.54 0.99940 ± 0.00014 5 – 1000 ≤ 0.01 0.988
54Mn 312.29 ± 0.26 834.848 0.999746 ± 0.000011 5 – 1000 ≤ 0.15 0.985
57Co 271.80 ± 0.05 122.061 0.8551 ± 0.0006 5 – 3700 ≤ 0.15 0.967
60Co 1925.23 ± 0.27 1332.5 0.999826 ± 0.000006 5 – 3700 ≤ 0.1 0.988
88Y 106.625 ± 0.024 1836.066 0.9938 ± 0.0003 5 – 1000 ≤ 0.1 0.991
109Cd 461.4 ± 1.2 88.034 0.03626 ± 0.00020 5 – 1000 ≤ 0.001 0.965
133Ba 3848.7 ± 1.2 356.014 0.6205 ± 0.0019 5 – 3700 ≤ 0.001 0.977
137Cs 10990 ± 40 661.66 0.8499 ± 0.0020 5 – 1000 ≤ 0.05 0.983
152Eu 4941 ± 7 1408.006 0.2085 ± 0.0009 5 – 1000 ≤ 0.15 0.988
241Am 157850 ± 230 59.537 0.3578 ± 0.0009 5 – 370 ≤ 0.05 0.962
* The nominal value of the radionuclide activity in the source within the specified limits is determined by the consumer when the source is ordered. Tolerance on activity -10 ÷ +30 %.
** The ratio of the total activity of impurity radionuclides to the activity of the basic radionuclide in the source.
*** Coefficients of the photon radiation transmission in source:
  • The source is always used only in one version — the working (radiating) surface is on the side opposite to the marking.
  • To determine the transmission coefficients, experimental data and interpolation and extrapolation data were used.
  • Transmission coefficients for other energy lines are calculated by interpolation.
Limit of error of measuring result for confidence probability р = 0.95: 7 или 3 % — at certification or attestation in accredited metrological, respectively.

Recommended working life
Radionuclide Recommended working life, years
241Am 3
88Y 2
54Mn, 57Co, 109Cd 2.5
22Na, 60Co, 133Ba, 137Cs, 152Eu 5

Request

Disk type Sources ОSGI-P

 

 

Application

OSGI-P sources are used for efficiency and energy calibration of gamma-spectrometric equipment, testing of ionizing chambers and scintillation counters. Robust design is suitable for “in field” calibrations and tests.

Description

Source is a transparent disc with diameter 25 mm and height 3 mm. Radionuclide is deposited on active part made of light ceramic pellet. Active part is mounted in center of acrylic capsule and sealed with epoxy resin. Dimensions of active part are 2 mm in diameter and 1 mm in height.

Certificates and documentation

  • NRC Certificate SSDR LA-1491-S-106-S OSGI-RT Refernce Sources EN
  • Pattern approval certificate of measuring instruments ОС.С.38.001.А No 72829 RU

Radionuc­lide Half-life, days Photon energy, keV Photons per 100 disintegration Activity, kBq * Impurities, % ** Coeffi­cients of the photon radia­tion trans­mis­sion ***
22Na 950.57 ± 0.23 1274.54 0.99940 ± 0.00014 5 – 1000 ≤ 0.01 0.988
44Ti 21915 ± 400 67.884 0.930 ± 0.020 5 – 100 ≤ 0.001 0.963
54Mn 312.29 ± 0.26 834.848 0.999746 ± 0.000011 5 – 1000 ≤ 0.15 0.985
57Co 271.80 ± 0.05 122.061 0.8551 ± 0.0006 5 – 3700 ≤ 0.15 0.967
60Co 1925.23 ± 0.27 1332.5 0.999826 ± 0.000006 5 – 3700 ≤ 0.1 0.988
65Zn 243.86 ± 0.20 1115.55 0.5060 ± 0.0022 5 – 1000 ≤ 0.2 0.987
88Y 106.625 ± 0.024 1836.066 0.9938 ± 0.0003 5 – 1000 ≤ 0.1 0.991
109Cd 461.4 ± 1.2 88.034 0.03626 ± 0.00020 5 – 1000 ≤ 0.001 0.965
113Sn 115.09 ± 0.04 391.71 0.6494 ± 0.0017 5 – 100 ≤ 0.01 0.978
133Ba 3848.7 ± 1.2 356.014 0.6205 ± 0.0019 5 – 3700 ≤ 0.001 0.977
134Cs 753.5 ± 1.0 604.7 0.97650 ± 0.00018 5 – 300 ≤ 0.01 0.982
137Cs 10990 ± 40 661.66 0.8499 ± 0.0020 5 – 1000 ≤ 0.05 0.983
139Ce 137.642 ± 0.020 165,86 0.7990 ± 0.0004 5 – 1000 ≤ 0.1 0.969
152Eu 4941 ± 7 1408.006 0.2085 ± 0.0009 5 – 1000 ≤ 0.15 0.988
153Gd 240.4 ± 1 97.431 0.29 5 – 500 ≤ 0.2 0.965
207Bi 11800 ± 300 569.7 0.9776 ± 0.0003 5 – 100 ≤ 0.2 0.982
228Th 698.6 ± 0.23 2614 0.99754 ± 4 5 – 50 ≤ 0.2 0.998
241Am 157850 ± 230 59.537 0.3578 ± 0.0009 5 – 370 ≤ 0.05 0.962
243Am 2692000 ± 8000 74.66 0.672 5 – 50 < 5 0.964
* The nominal value of the radionuclide activity in the source within the specified limits is determined by the consumer when the source is ordered. Tolerance on activity -10 ÷ +30 %.
** The ratio of the total activity of impurity radionuclides to the activity of the basic radionuclide in the source.
*** Coefficients of the photon radiation transmission in OSGI-P source:
  • The source is always used only in one version — the working (radiating) surface is on the side opposite to the marking.
  • To determine the transmission coefficients, experimental data and interpolation and extrapolation data were used.
  • Transmission coefficients for other energy lines are calculated by interpolation.
Limit of error of measuring result for confidence probability р = 0.95: 7 или 3 % — at certification or attestation in accredited metrological, respectively. ISO classification: С34343

Recommended working life
Radionuclide Recommended working life, years
228Th, 241Am, 243Am 6
88Y, 113Sn, 139Ce 4
54Mn, 57Co, 65Zn, 109Cd, 153Gd 5
22Na, 44Ti, 60Co, 133Ba, 134Cs, 137Cs, 152Eu, 207Bi, 210Pb 10

Request

Gamma Standards ОSGI-RT

 

 

Application

Gamma standard sources are used as working standards for verification and graduation of photon measuring equipment, for certification of measuring methods and measurement accuracy control of photon emission. In particular, the set is intended for testing and calibration of precision instruments, spectrometers and radiometers, ionization chambers and scintillation counters.

Description

The source is produced in the form of a flat round capsule made of aluminum, 25 mm in diameter (29 mm by special order) and 3 mm thick. The source active part of less than 3 mm in diameter is embedded between two polyimide foils with total thickness of 100 ± 10 μm.

Radionuclide Decay mode Half-life, days Photon energy, keV Photons per 100 disintegration Activity, kBq * Equivalent dose rate, μSv/h **
22Na EC 950.57 ± 0.23 511 (annihil)
1274.537 ± 0.003		 1.798 ± 0.002
0.99940 ± 0.00014		 1 – 1000 ≤ 35.0
44Ti EC 21900 ± 15

68.868 ± 0.014
78.36 ± 0.03
511.00 (Annihil)
1157.020 ± 0.015

 0.930 ± 0.0015
0.964 ± 0.0011
184.54 ± 0.10
0.999 ± 0.004		 1 – 300 ≤ 10.2
54Mn EC 312.29 ± 0.26 834.838 ± 0.005 0.999746 ± 0.000011 1 – 1000 ≤ 14.0
55Fe EC 1002.7 ± 2.3 (Mn Kα) 5,8988
(Mn Kβ) 6.49-6.54		 0.1656 ± 0.0027
0.0340 ± 0.007		 1 – 1000 ≤ 0.02
57Co EC 271.80 ± 0.05 14.41295 ± 0.00031
122.06065 ± 0.00012
136.47356 ± 0.00029		 0.0915 ± 0.0017
0.8551 ± 0.0006
0.1071 ± 0.0015		 1 – 1000 ≤ 1.7
60Co β- 1925.23 ± 0.27 1173.228 ± 0.003
1332.492 ± 0.004		 0.9985 ± 0.0003
0.999826 ± 0.000006		 1 – 500 ≤ 19.0
65Zn EC 243.86 ± 0.20 511 (annihil)
1115.539 ± 0.002		 0.0284 ± 0.0004
0.5060 ± 0.0022		 1 – 1000 ≤ 10.0
88Y EC 106.625 ± 0.024 898.036 ± 0.004
1836.052 ± 0.013		 0.9390 ± 0.0023
0.9938 ± 0.0003		 1 – 1000 ≤ 38.8
109Cd EC 461.4 ± 1.2 88.0336 ± 0.0011 0.03626 ± 0.00020 1 – 1000 ≤ 0.04
113Sn EC 115.09 ± 0.04 391.698 ± 0.003 0.6494 ± 0.0017 1 – 500 ≤ 2.2
133Ba EC 3848.7 ± 1.2 80.9979 ± 0.0011
276.3989 ± 0.0012
302.8508 ± 0.0005
356.0129 ± 0.0007
383.8485 ± 0.0012		 0.329 ± 0.003
0.0716 ± 0.0005
0.1834 ± 0.0013
0.6205 ± 0.0019
0.0894 ± 0.0006		 1 – 1000 ≤ 8.8
134Cs β- 753.5 ± 1.0 569.327 ± 0.003
604.720 ± 0.003
795.83 ± 0.03		 0.1538 ± 0.0004
0.97650 ± 0.00018
0.855 ± 0.003		 1 – 300 ≤ 7.5
137Cs β- 10990 ± 40 661.657 ± 0.003 0.8499 ± 0.0020 1 – 1000 ≤ 10.0
139Ce EC 137.642 ± 0.020 165.8575 ± 0.0011 0.7990 ± 0.0004 1 – 1000 ≤ 6.3
152Eu EC 4941 ± 7 121.7817 ± 0.0003
344.2785 ± 0.0012
778.9045 ± 0.0024
964.072 ± 0.018
1085.837 ± 0.010
1112.076 ± 0.003
1408.013 ± 0.003		 0.2841 ± 0.0013
0.2658 ± 0.0012
0.1296 ± 0.0006
0.1462 ± 0.0006
0.1013 ± 0.0006
0.1340 ± 0.0006
0.2085 ± 0.0009		 1 – 1000 ≤ 20.0
153Gd EC 240.4 ± 1 97.431 ± 0.021
103.18012 ± 0.00017		 0.29
0.211 ± 0.006		 1 – 500 ≤ 1.0
207Bi EC 11800 ± 300 569.698 ± 0.002
1063.656 ± 0.003
1770.228 ± 0.009		 0.9776 ± 0.0003
0.7458 ± 0.0049
0.0687 ± 0.0002		 1 – 100 ≤ 2.6
228Th α 670 ± 2 39.86 ÷ 2614.53 1.03 ÷ 36.06 1 – 100 ≤ 0.3
241Am α 157850 ± 230 26.3446 ± 0.0002
59.5409 ± 0.0001		 0.0240 ± 0.0003
0.3578 ± 0.0009		 1 – 300 ≤ 0.12
243Am α 2692000 ± 8000 43.53 ± 0.02
74.66 ± 0.02		 0,0590 ± 0.0015
0.672		 1 – 50 ≤ 0.04
* Other activities are available on request. The nominal value of the radionuclide activity in the source within the specified limits is determined by the consumer when the source is ordered. Tolerance on activity ±20 %
Equivalent dose rate - equivalent dose rate of photon radiation at a distance of 0.1 m.
Limit of error of measuring result for confidence probability р = 0.95: 7, 3 or 1.5 % — at certification, attestation in accredited metrological centers or attestation as working standards of the 0-th category, respectively.
ISO classification: С35242
** Estimated for maximum activity at 10 cm from source surface.

Recommended working life and Intercalibration interval *
Radionuclide Recommended working life, years Intercalibration interval, years
228Th, 241Am, 243Am 5 (with activity less than 10 kBq)
3 (with activity more than 10 kBq)		 2
1
88Y, 113Sn, 139Ce 4 1
54Mn, 57Co, 65Zn, 109Cd, 153Gd 5 2
22Na, 55Fe, 134Cs 10 2
44Ti, 60Co, 137Cs, 133Ba, 152Eu, 207Bi 12 2
* Recommended working life and intercalibration interval of the multinuclide source are determined by the shortest working life and interval of individual radionuclides in the source. When supplying sources with a higher activity of the radionuclide, in agreement with the customer, a reduction of recommended working life is allowed.

Request

Mixed Radionuclide

 

 

Description

The source is produced in the form of a flat round capsule made of aluminum, 25 mm in diameter (29 mm by special order) and 3 mm thick. The source active part of less than 3 mm in diameter is embedded between two polyimide foils with total thickness of 100 ± 10 μm. The active spot of the source contains 4 nuclides:


88Y – 370 kBq, 133Ba – 37 kBq, 152Eu – 37 kBq, 241Am – 37 kBq.

 

Advantages
  • all calibration data is collected in a single pass, which reduces systematic errors.
  • all components are measured simultaneously.
  • time savings compared to calibration with single radionuclide sources.
Features

At least 20 energy lines are required for efficiency calibration of semiconductor detector of HPGe and Ge(Li) types. Source is designed for 2 years useful work.

Advantages

  • All calibration data are acquired in one run. This reduces systematic mistakes, while all components are measured at the same time and exposition.

  • Time saving compare to calibration with single nuclide sources.

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Radionuclide Decay mode Half-life, days Photon energy, keV Photons per 100 disintegration Activity, kBq * Exposure dose rate, μSv/h **
88Y + EC 106.625 ± 0.024 898.036 ± 0.004
1836.052 ± 0.013		 0.9390 ± 0.0023
0.9938 ± 0.0003		 370 + 18
133Ba + EC 3848.7 ± 1.2 80.9979 ± 0.0011
276.3989 ± 0.0012
302.8508 ± 0.0005
356.0129 ± 0.0007
383.8485 ± 0.0012		 0.329 ± 0.003
0.0716 ± 0.0005
0.1834 ± 0.0013
0.6205 ± 0.0019
0.0894 ± 0.0006		 37 +
152Eu + EC 4941 ± 7 121.7817 ± 0.0003
344.2785 ± 0.0012
778.9045 ± 0.0024
964.072 ± 0.018
1085.837  ± 0.010
1112.076 ± 0.003
1408.013 ± 0.003		 0.2841 ± 0.0013
0.2658 ± 0.0012
0.1296 ± 0.0006
0.1462 ± 0.0006
0.1013 ± 0.0006
0.1340 ± 0.0006
0.2085 ± 0.0009		 37 +
241Am α 157850 ± 230 26.3446 ± 0.0002
59.5409 ± 0.0001		 0.0240 ± 0.0003
0.3578 ± 0.0009		 37
* Other activities are available on request. The nominal value of the radionuclide activity in the source within the specified limits is determined by the consumer when the source is ordered. Tolerance on activity ±20 %
** Exposure dose rate - equivalent dose rate of photon radiation at a distance of 0.1 m.
Recommended working life and intercalibration interval of the multinuclide source are determined by the shortest working life and interval of individual radionuclides in the source. When supplying sources with a higher activity of the radionuclide, in agreement with the customer, a reduction of recommended working life is allowed.
Limit of error of measuring result for confidence probability р = 0,95: 7, 3 or 1.5 % — at certification, attestation in accredited metrological centers or attestation as working standards of the 0-th category, respectively.
ISO classification: С35242

Request

Sources for NaI-spectrometers

Application

Sources OSGI-P are used for activity and energy calibration of gamma-spectrometric equipment, testing of ionization chambers and scintillation counters. Rugged design suitable for calibration and field testing.

Description

Source is a transparent disc with diameter 25 mm and height 3 mm. Radionuclide is deposited on active part made of light ceramic pellet. Active part is mounted in center of acrylic capsule and sealed with epoxy resin. Dimensions of active part are 2 mm in diameter and 1 mm in height.

Radionuc­lide Half-life, days Photon energy, keV Photons per 100 disintegration Activity, kBq * Impurities, % ** Coeffi­cients of the photon radia­tion trans­mis­sion ***
22Na 950.57 ± 0.23 1274.54 0.99940 ± 0.00014 5 – 1000 ≤ 0.01 0.988
54Mn 312.29 ± 0.26 834.848 0.999746 ± 0.000011 5 – 1000 ≤ 0.15 0.985
57Co 271.80 ± 0.05 122.061 0.8551 ± 0.0006 5 – 3700 ≤ 0.15 0.967
60Co 1925.23 ± 0.27 1332.5 0.999826 ± 0.000006 5 – 3700 ≤ 0.1 0.988
137Cs 10990 ± 40 661.66 0.8499 ± 0.0020 5 – 1000 ≤ 0.05 0.983
241Am 157850 ± 230 59.537 0.3578 ± 0.0009 5 – 370 ≤ 0.05 0.962
* The nominal value of the radionuclide activity in the source within the specified limits is determined by the consumer when the source is ordered. Tolerance on activity -10 ÷ +30 %.
** The ratio of the total activity of impurity radionuclides to the activity of the basic radionuclide in the source.
*** Coefficients of the photon radiation transmission in OSGI-P source:
  • The source is always used only in one version — the working (radiating) surface is on the side opposite to the marking.
  • To determine the transmission coefficients, experimental data and interpolation and extrapolation data were used.
  • Transmission coefficients for other energy lines are calculated by interpolation.
Limit of error of measuring result for confidence probability р = 0.95: 7 или 3 % — at certification or attestation in accredited metrological, respectively.
ISO classification: С34343

Recommended working life
Radionuclide Recommended working life, years
241Am 6
54Mn, 57Co 5
22Na, 60Co, 137Cs 10

Request

Sources