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Comparative Study
. 2018 May 1;59(3):286-290.
doi: 10.1093/jrr/rrx099.

Comparison of calculated beta- and gamma-ray doses after the Fukushima accident with data from single-grain luminescence retrospective dosimetry of quartz inclusions in a brick sample

Affiliations
Comparative Study

Comparison of calculated beta- and gamma-ray doses after the Fukushima accident with data from single-grain luminescence retrospective dosimetry of quartz inclusions in a brick sample

Satoru Endo et al. J Radiat Res. .

Abstract

To estimate the beta- and gamma-ray doses in a brick sample taken from Odaka, Minami-Soma City, Fukushima Prefecture, Japan, a Monte Carlo calculation was performed with Particle and Heavy Ion Transport code System (PHITS) code. The calculated results were compared with data obtained by single-grain retrospective luminescence dosimetry of quartz inclusions in the brick sample. The calculated result agreed well with the measured data. The dose increase measured at the brick surface was explained by the beta-ray contribution, and the slight slope in the dose profile deeper in the brick was due to the gamma-ray contribution. The skin dose was estimated from the calculated result as 164 mGy over 3 years at the sampling site.

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Figures

Fig. 1.
Fig. 1.
(a) Mirror condition calculation, (b) top view and (c) side view of the calculation geometry.
Fig. 2.
Fig. 2.
Air dose rates of (a) beta rays and (b) gamma rays over time.
Fig. 3.
Fig. 3.
Comparison of the calculated beta rays (chain line), gamma rays (dotted line), beta + gamma rays (solid line), dose averaged over sample depth (dashed histogram), and data measured by Stepanenko et al. (open circles).

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