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Journal Articles

Experimental study on the localization and estimation of radioactivity in concrete rubble using image reconstruction algorithms

Takai, Shizuka; Namekawa, Masakazu*; Shimada, Taro; Takeda, Seiji

IEEE Transactions on Nuclear Science, 69(7), p.1789 - 1798, 2022/07

 Times Cited Count:0 Percentile:0.01(Engineering, Electrical & Electronic)

To reduce a large amount of contaminated concrete rubble stored in the Fukushima Daiichi Nuclear Power Station site, recycling low-radioactivity rubble within the site is a possible remedy. To promote recycling while ensuring safety, not only the average radioactivity but also the radioactivity distribution of concrete rubble should be efficiently evaluated because the details of rubble contamination caused by the accident remain unclear and likely include hotspots. However, evaluating inhomogeneous contamination of thick and/or dense materials is difficult using previous measurement systems, such as clearance monitors. This study experimentally confirmed the potential applicability of image reconstruction algorithms for radioactivity distribution evaluation in concrete rubble filled in a chamber. Radiation was measured using plastic scintillation fiber around the chamber (50 $$times$$ 50 $$times$$ 40 cm$$^{3}$$). Localized hotspots were simulated using standard sources of $$^{137}$$Cs, which is one of the main nuclides of contaminated rubble. The radioactivity distribution was calculated for 100 or 50 voxels (voxel size: (10 cm)$$^{3}$$ or 10 $$times$$ 10 $$times$$ 20 cm$$^{3}$$) constituting the chamber. For 100 voxels, inner hotspots were undetected, whereas, for 50 voxels, both inner and surface hotspots were reconstructible. The distribution evaluated using the maximum likelihood expectation maximization algorithm was the most accurate; the average radioactivity was estimated within 70% accuracy in all seven cases.

Oral presentation

Introduction of external drift kriging into the program for estimating radioactivity distribution ESRAD code for supporting final survey of site release

Shimada, Taro; Nabekura, Nobuhide*; Takeda, Seiji

no journal, , 

It is necessary to confirm that the public radiation exposure dose by residual radioactivity is less than the criteria after site release at the completion of decommissioning of nuclear facilities. In order to obtain the radioactivity distribution in the site to evaluate the public dose, we have been developing a computer code, ESRAD, which estimates the radioactivity distribution from limited measurement data of radioactivity of soil in the site using the kriging. In this study, we improved the code by introducing the external drift kriging where dose rate distribution obtained before final survey was used as supplement information. Some calculations were carried out supposing hypothetical radioactivity distribution. As a result, the external drift kriging using dose rate distribution may improve the estimation results rather than the ordinary kriging.

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