In this study we have investigated the possibility of processing waste rubber gloves using pyrolysis. Y-zeolite catalyst was employed to upgrade the pyrolysis products to give higher yields of valuable aromatic compounds such as toluene and xylenes. The composition of the pyrolysis products was determined using GC-MS, GC-FID, GC-TCD, and FT-IR. It was found that when rubber gloves were pyrolysed in the absence of a catalyst, the pyrolysis oil consisted mainly of limonene and oligomers of polyisoprene. When Y-zeolite was added to the reaction system, the yields of toluene, xylene, methylbenzenes, ethylbenzenes, and naphthalenes increased dramatically. The Y-zeolite also catalysed the decomposition of limonene, which was absent from the catalytic pyrolysis products. The presence of the Yzeolite catalyst also increased the yield of hydrocarbon gases. The tests were carried out at both 380°C and 480°C and it was found that the higher reaction temperature led to increased yields of all the major compounds, both in the presence and absence of the Y-zeolite catalyst.
A fundamental problem in studying a hydrological system is that most of the reaction takes place underground. Precipitation Runoff demonstrating of the Johan River basin was carried out using HEC-HMS technique. The model can improve decision-making about the hydrological problem, whether that be in water resources planning, flood protection and mitigation of contamination. The result shows that the rainfall-runoff model for the Bukit Kledang basin is slow depending on the relative travel time of basin and also associated with soil type, land used, multiple storms and seasonality.
An investigation on the out-core neutron flux in the Reactor TRIGA PUSPATI is carried out in this work to determine whether the thermal and/or fast neutron from the core would cause burn-up of the irradiated fuel stored in the same vicinity of the reactor core. The storage rack is positioned at 1 m from the central thimble. MCNPX code is used to calculate the fast and thermal neutron flux at 750 kW reactor power using 10 cm 10 cm 10 cm mesh while MATLAB model on 20 cm 20 cm mesh model is used to plot the axial and radial distribution of the neutron flux density. The results show that the thermal neutrons occurred at energy lower than 1 10 6 MeV and traveled to a maximum distance of 78 cm. The greatest flux for thermal and fast neutrons is 1 10 13 n.cm 2 .s 1 and 5 10 13 n.cm 2 .s 1 respectively. The fission-rate of the fuel in the core is determined to be 3.18 10 14 particle/s compared to 1.51 10 7 particle/s of the irradiated fuel in the storage rack. The burn-up of the fuel in the storage rack is in the order of micrograms and therefore is negligible. It is concluded that neutron flux from the core would not impart burn up effect onto the irradiated fuel stored at the storage rack in the reactor pool.
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