Radiation Measurement of a Operational CANDU Reactor Fuel Handling Machine using Semiconductor Sensors (ICCAS 2003)

  • Lee, Nam-Ho (Robotics Lab., Korea Atomic Energy Research Institute) ;
  • Kim, Seung-Ho (Department of Electrical Engineering, ChoongNam University) ;
  • Kim, Yang-Mo (Department of Electrical Engineering, ChoongNam University)
  • Published : 2003.10.22

Abstract

In this paper, we measured the radiation dose of a fuel handling machine of the CANDU type Wolsong nuclear reactor directly during operation, in spite of the high radiation level. In this paper we will describe the sensor development, measurement techniques, and results of our study. For this study, we used specially developed semiconductor sensors and matching dosimetry techniques for the mixed radiation field. MOSFET dosimeters with a thin oxide, that are tuned to a high dose, were used to measure the ionizing radiation dose. Silicon diode dosimeters with an optimum area to thickness ratio were used for the radiation damage measurements. The sensors are able to distinguish neutrons from gamma/X-rays. To measure the radiation dose, electronic sensor modules were installed on two locations of the fuel handling machine. The measurements were performed throughout one reactor maintenance cycle. The resultant annual cumulative dose of gamma/X-rays on the two spots of the fuel handling machine were 18.47 Mrad and 76.50 Mrad, and those of the neutrons were 17.51 krad and 60.67 krad. The measured radiation level is high enough to degrade certain cable insulation materials that may result in electrical insulation failure.

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