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Feasibility study for visualization of radioactive material distribution in Fukushima nuclear reactor based on OSL technology

Nanda, N.*; 宇佐美 博士; 森下 祐樹  ; 杉田 武志*; 鳥居 建男 ; 安田 仲宏*

Nanda, N.*; Usami, Hiroshi; Morishita, Yuki; Sugita, Takeshi*; Torii, Tatsuo; Yasuda, Nakahiro*

The accident in Fukushima Daiichi Nuclear Power Plants (FDNPP) on March 11, 2011 released large amounts of radionuclides into the atmosphere. There are still contaminated areas with considerable amounts of radioactive substances in Fukushima prefecture. Some of the most contaminated areas are the reactor buildings, and very large amounts of radionuclides (mainly $$^{137}$$Cs) have been detected from measurements inside the reactor buildings. Therefore, to execute decommissioning tasks in the reactor buildings, radiation distribution measurements inside the buildings are necessary. For the decommissioning and decontamination processes, it is necessary to know the radiation levels inside the reactor and other buildings. To measure and monitor gamma-ray radiation is therefore important. There have been several attempts to measure the radiation distributions inside the reactor buildings by using gamma-ray detectors with a wide Field of View, which can quantitatively visualize the Cs contamination. These active detectors can measure the radiation distribution rapidly to identify the locations of the radiation sources. However, with the large amounts of radionuclides still inside the reactor buildings, it is difficult to obtain information about local dose distributions. Gamma spectrometers or radiation area monitors are not always working. They are also easily broken, and not resilient to high dose radiation fields. In this research, an integral type gamma-ray imager based on Optically Stimulated Luminescence (OSL) technology are proposed. OSL has been used extensively for personal radiation dosimetry for many years. By combining it with a Pinhole camera principle, this passive detector is capable to visualize the position of radioactive substances. Therefore, to optimize the structural design and detection measurement system we are using the simulation code PHITS (Particle and Heavy Ion Transport code System) and then compare the calculated results with the experiments.

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