Abstract
An activated concrete sample was counted at different source to detector distances with CdZnTe and HPGe detectors. The experimental count rates for different radionuclides were converted to dose rate using Monte Carlo code and compared with the Measured dose rates obtained using digital survey meter. The results agreed well for both the detectors. This indicates that CdZnTe detector having a better portability but poorer resolution than HPGe detector can be effectively used for online monitoring of radioactivity as well as dose rate calculations.
Original language | English |
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Pages (from-to) | 461-464 |
Number of pages | 4 |
Journal | Journal of Radioanalytical and Nuclear Chemistry |
Volume | 294 |
Issue number | 3 |
DOIs | |
State | Published - 1 Dec 2012 |
Externally published | Yes |
Keywords
- CdZnTe detector
- Efficiency
- Gamma ray
- MCNP code
- PHT pipeline
ASJC Scopus subject areas
- Analytical Chemistry
- Nuclear Energy and Engineering
- Radiology Nuclear Medicine and imaging
- Pollution
- Spectroscopy
- Public Health, Environmental and Occupational Health
- Health, Toxicology and Mutagenesis