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Abstract  

The fission track registration efficiency of diethylene glycol bis allyl carbonate (dioctyl phthalate doped) [CR-39 (DOP)] solid state nuclear track detector (SSNTD) in solution medium (K wet) has been experimentally determined and is found to be (9.7 ± 0.5) × 10−4 cm. This is in good agreement with the values of other SSNTDs. The gamma irradiation effects in the dose range of 50.0–220.0 kGy on the bulk etch rate, V b and the activation energy for bulk etching, E of this solid state nuclear track detector (SSNTD) have also been studied. It is observed that the bulk etch rates increase and the activation energies for bulk etching decrease with the increase in gamma dose. These results have been explained on the basis of scission of the detector due to gamma irradiation.

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GWP Critical temperature [K] Critical Pressure [MPa] Boiling Point [K] Wet ACZ 744 CO 2 A1 0 1 304.1282 7.3773 194.75 2.3 Thermodynamic analysis A calculation was performed to find the efficiency of the CO 2 power cycle with the temperature variation

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