Registration of fission fragments in glass mica and plastics

The registration of fission fragments in various materials commonly available in Thailand, such as glass, mica and plastics were studied. A foil of depleted uranium of 99,9% chemical purity was used with an americium/beryllium source (neutron flux in the order of 104 neutrons/cm-2 sec-1). The etching times by the chemical reagents to produce tracks visible in an optical microscope were listed. The registration efficiencies of the materials obtained from high to low were mylar, makrofol, mica and glass respectively. The paper may be used as a guide for the study of neutron dose and flux in the future