The GRAETZ CoMo-170 ZS is a powerful, mobile and battery or accumulator operated contamination monitor for highly sensitive nuclide-related measurement of surfaces for α-, β- and γ-contamination when handling ionizing radiation. The one-hand measuring system has a detector area of 170 cm2 and automatically detects whether α-radiation is present. The measured value display is optionally pulses per second (Ip/s) or nuclide-related in Becquerel (Bq) and Bq/cm2. The system technology of the CoMo-170 ZS version is identical to the standard version of the CoMo-170 mobile contamination monitor. This system has proven itself in the practical use of radiation protection with approximately 6,000 devices. The ZS version differs essentially in the software and is optimized specifically for civil defense and disaster control use.
- Easy to use one-hand measuring system
- Fast inspection of large surfaces due to large detector area
- Optical and acoustic warning when the set warning thresholds (dose and dose rate) are exceeded.
- High reliability due to constant self-monitoring
- Small, handy housing, well decontaminable
Technical Data
Detector type | Thin Film Plastic Scintillation Detector with ZnS Coating | |
Detector size | 170 cm² | |
Display ranges | α-channel | up to 5,000 Ip/s (Am-241) |
β-γ-channel | up to 50,000 Ip/s (Cs-137) | |
Measuring ranges | α-channel | up to 2,500 Ip/s (Am-241) |
β-γ-channel | up to 20,000 Ip/s (Cs-137) | |
Zero effect | α-channel | approx. 0.1 Ip/s |
β-γ-channel |
approx. 15 – 20 Ip/s | |
Zero effect subtraction | Decon P | Automatic zero effect measurement and subtraction, zero effect measurement time parameterizable |
ATF | Automatic zero effect measurement and subtraction, zero effect measurement time parameterizable, net or gross measurement selectable | |
Dimensions | approx. 280 × 125 × 135 mm | |
Weight (incl. batteries) |
approx. 800 g | |
Protection class | IP54 (Protected against splashing water) |
For detailed technical data, please refer to our product data sheet for this article.
Efficiencies for different radionuclides
(Mean values from measurements with 100 cm2 specimens) The nuclide-related efficiencies of the scintillation detector are comparable to the efficiencies of conventional counting tubes.
C-14 | approx. 14 % | Tc-99m | approx. 3 % |
F-18 | approx. 18 % | In-111 | approx. 8 % |
P-32 | approx. 25 % | I-123 | approx. 7 % |
S-35 | approx. 5 % | I-125 | approx. 12 % |
Cl-36 | approx. 42 % | I-131 | approx. 21 % |
K-40 | approx. 30 % | Cs-137 | approx. 35 % |
Co-57 | approx. 7 % | Au-198 | approx. 23 % |
Co-60 | approx. 27 % | Tl-204 | approx. 43 % |
Sr-89 | approx. 27 % | Am-241 α | approx. 22 % |
Sr-90 / Y-90 (related to Sr-90) | approx. 42 % | P-238 α | approx. 12 % |
U-238 α | approx. 26 % |