AT1117M Radiation Monitor with BDKN-06 and a set of spherical moderators
Measurement of neutron radiation characteristics to reconstruct the energy distribution of neutron flux density.
Obtained energy distribution of neutron flux density is used to calculate such values as:
– Integral neutron flux density
– Average energy of neutron radiation by spectrum
– Average energy of neutron radiation by dose
– Dose equivalent per unit flux density
– Dose equivalent
– Effective dose
- Ready-to-use measurement procedures
- Advanced set of spherical polyethylene moderators is available with the following diameters: 3.5″; 4.5″; 5″; 7″; 9″; 9.5″
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Specification
|
AT1117M Radiation Monitor with BDKN-06 Detection Unit |
| Detector |
3He proportional counter |
| Energy range |
0.025 eV – 20 MeV |
| Measurement range of neutron count rate |
0.01 – 5·104 cps |
| Limit of tolerable intrinsic relative error (P=0.95) for neutron measurement |
±10% |
| Detection range of neutron flux density |
1·10-16 – 5·1012 neutron/(s·cm2·MeV) |
| Typical neutron sensitivity |
1 cps/(neutron·s-1·cm-2) [Pu-Be] |
| Relative sensitivity due to the incidence angle of neutrons |
up to -25% |
| Protection class |
IР64 |
| Overall dimensions, weight |
550x254x254 mm, 10 kg
(with Ø254 mm (Ø10″) spherical moderator without tripod) |
Design and specifications are subject to change without notice.
For details please refer to the datasheet.
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