Prediction and estimation of dose around Pressure Containment Vessel containing BWR plant fuel debris (The 12th International Conference on Radiation Shielding (ICRS-12) and the 17th Topical Meeting of the Radiation Protection and Shielding Division of ANS (RPSD-2012)) -- (Accident of Fukushima Nuclear Power Plant and Its Influence)

*As part of decommissioning efforts of the Fukushima Daiichi nuclear power station, removing the fuel debris from the Pressure Containment Vessel (PCV) and its preparation tasks are planned. In order to conduct efficiently above tasks, it is important to predict the dose rate in the work areas for the radiation workers. However, the locations of fuel debris have not necessarily been confirmed and the radiation measurement data of inside the PCV are not sufficiently obtained in the present. Besides the effect of dose rate due to the lump debris, the PCV area is supposedly considered a high dose rate due to the contaminated radionuclide in the stagnant water and on the surface inside the PCV. In order to evaluate dose rate due to radiation emitted from the fuel debris and other radiation sources inside the PCV, we made calculations using ANISN and DORT.