Radiation Protection Dosimetry Advance Access originally published online on April 5, 2006
Radiation Protection Dosimetry 2006 120(1-4):470-474; doi:10.1093/rpd/nci672
| ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
Extremely high dose neutron dosimetry using CR-39 and atomic force microscopy
1 National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage, Chiba 263-8555, Japan
2 Atomic Energy Research Institute, Kinki University, 3-4-1 Kowakae, Higashi-Osaka, Osaka 577-0818, Japan
3 Nagase Landauer, Ltd., 11-6 Hisamatsu-cho, Nihonbashi, Chuou-ku, Tokyo 103-8487, Japan
4 Chiyoda Technol Corporation, 3681 Narita-cho, Oarai-machi, Higashi Ibaraki Gun, Ibaraki 311-1313, Japan
* Corresponding author: nyasuda{at}nirs.go.jp
Atomic force microscopy (AFM) has been applied to the analysis of CR-39 nuclear track detectors for high dose neutron dosimetry. As a feasible study to extract the neutron dose, we have employed a 239PuBe neutron source with the traditional track density measurement of recoil proton etch pits from a high density polyethylene (CH2) radiator. After very short etching (
1 µm), etch pit densities were measured as a function of neutron fluence (neutron dose) up to 1.4 x 1010 cm2 (6.6 Sv). Neutron sensitivity was also measured to be 6.6 x 104. Maximum measurable neutron dose was estimated to be
200 Sv by measuring the fraction of the total image area occupied by the etch pits.