Overview:
It is designed to measure the ambient dose equivalent of neutrons. Its spherical design complies with the recommendations of the International Commission on Radiological Protection(ICRP)and provides excellent energy and angular response. It can be used as a portable or fixed instrument. The device uses a moderating body composed of carbon-doped polyethylene and cadmium-doped heavy metals, combined with a He-3 neutron counter tube, to optimize the detector’s energy response. The parameters of the moderating sphere are calculated using MCNP simulations. It is mainly applied in areas such as reactors, nuclear fuel cycles in nuclear technology applications, spent fuel transportation and recycling, and nuclear, biological, and chemical defense systems
Features:
- Multipurpose: Can be used as a portable instrument or for fixed monitoring.
- Moderation parameters calculated using MCNP simulations for improved energy response.
- Spherical design for enhanced angular response.
- Wide energy response range with energy compensation.
- Excellent environmental adaptability with an extremely low false alarm rate.
Technical Specifications:
| Main Unit | |
| Detector Type | Built-in GM tube |
| Dose Rate Range | 100 nSv/h to 100 mSv/h |
| Energy Range | 45 keV to 3 MeV |
| Alarm | Continuously adjustable threshold with sound and light alarms |
| Battery Life | ≥ 24 hours |
| Data Connection | USB transmission |
| Neutron Probe | |
| Sensor | He-3 counter tube |
| Measurement Range | 0.01 µSv/h to 100 mSv/h |
| Energy Response Error | 0.5 to 2.0 (in the 50 keV to 10 MeV range) |
| Sensitivity | Reading < 40 µSv/h (10 mSv/h in 137-Csγ field) |
| Energy Range | Thermal neutron – 20 MeV |
| γ Sensitivity | Reading < 40 µSv/h (10 mSv/h in 137-Csγ field) |
| Angular Response | ±20% in all directions |
| Moderator Material | Polyethylene |
| Relative Inherent Error | ≤ 15% |
| Response Time | ≤ 5 seconds |






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