Numéro |
Radioprotection
Volume 49, Numéro 4, Octobre-Décembre 2014
|
|
---|---|---|
Page(s) | 261 - 268 | |
DOI | https://doi.org/10.1051/radiopro/2014016 | |
Publié en ligne | 26 septembre 2014 |
Article
An experimental study of detection limits and corresponding doses of IRSN in vivo monitoring vehicles in the case of post-accident scenarios
1 IRSN/PRP-HOM/SDI/LEDI, BP
17, 92262
Fontenay-aux-Roses,
France.
2 IRSN/PRP-CRI/SESUC/BSPA, BP
17, 92262
Fontenay-aux-Roses,
France.
Received:
18
March
2014
Accepted:
11
June
2014
The measurement performances of in vivo monitoring vehicles were studied considering an increase in the radiological background in areas where the population is not evacuated after a nuclear accident. The study focused on 137Cs and 131I Detection Limits (DLs) and corresponding doses, for adults and one-year-old children. These DLs for ground contamination were obtained experimentally using a grid of point sources. Then, the DLs and doses were calculated using the experimental data and a safety factor for two accident scenarios. For these scenarios the 137Cs DL corresponds to a committed effective dose of 0.02 mSv. The 131I DL corresponds to committed equivalent thyroid doses of 3 mSv (adult) and 30 mSv (one-year-old child). To guarantee a 45 mSv thyroid equivalent dose assessment for the child the surface activity of 131I + 132I + 133I should be below 1.6 MBq/m2. This study shows that the vehicles can operate in a contaminated area where the population is not evacuated. However, in such a case, the contamination level outside and inside the vehicle should be kept stable to guarantee efficient body counting.
Key words: in vivo monitoring / detection limit / post-accident management / ground contamination
© EDP Sciences, 2014
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