Business Process Improvement in Commercial Ship Division of PT. X: a Theory of Constraints Thinking Process Approach

PT. X as one of the biggest shipyard is facing a great challenge to keep its existence. One of its division which has the largest production capacity and expected contribution, is Commercial Ship Division. At 2011 it only fulfilled 23,1% of its target, which brought a huge loss to the corporate. That condition presses Commercial Ship Division to manage a continuous improvement in business process. Facing a constrained resources, all effort must be effectively and efficiently carried on. In this research, solution in business process improvement is approached using Theory of Constraints Thinking Process. From Current Reality Tree (CRT) diagram, the model of problem is acquired. Future Reality Tree (FRT) diagram is used to depict how injection influence the improvement. Transition Tree (TT) is assembled to arrange the necessary step for improvement or a road map

Studi Produksi Radioisotop Mo-99 Dengan Bahan Target Larutan Uranil Nitrat Pada Reaktor Kartini

STUDI PRODUKSI RADIOISOTOP Mo-99 DENGAN BAHAN TARGET LARUTAN URANIL NITRAT PADA REAKTOR KARTINI. Telah dilakukan analisis simulasi larutan U-nitrat sebagai target iradiasi neutron untuk produksi radioisotop Mo-99. Uranium dalam senyawa nitrat diperkaya dengan 20% berat U-235. Analisis simulasi dilakukan berdasarkan pada perhitungan program ORIGEN2 dimana variasi simulasi konsentrasi U-nitrat yang diuraikan dalam data komposisi unsur dalam larutan dijadikan masukan program ORIGEN2. Program ORIGEN2 digunakan untuk menghitung Perubahan komposisi unsur apabila larutan teriradiasi neutron dengan fluks 5x1011 n/cm2det dengan lama iradiasi mulai dari 1 hari sampai dengan 8 hari. Untuk menyederhanakan analisis dibuat representasi grafis terhadap hasil perhitungan terhadap parameter K~, Energi fisi, radioaktivitas MO-99 dan kontur peluruhan Mo setelah selesai iradiasi. Dari hasil analisis simulasi dapat disimpulkan bahwa radioisotop Mo-99 dapat diproduksi dengan melalui iradiasi larutan U-nitrat 102 g/l dengan uranium diperkaya 20% berat U-235 pada reaktor Kartini. Produksi yang dapat dicapai adalah 3.23 Ci Mo-99 per 300 cc larutan dengan lama iradiasi 5 hari. Daya thermal yang dibangkitkan dalam larutan selama proses iradiasi sebesar 89.3 watt didinginkan oleh sistem sirkulasi air kolam reaktor

Cadmium (Cd) Absorption and Phenol Content in Pogostemon Exposed to Heavy Metals

Patchouli (Pogostemon cablin Benth.) is an important plant used by industrial facilities to absorb cadmium (Cd) in polluted land. We performed an experiment using plant medium polluted with both Cd and lead (Pb) with added humic acid. The aims of this study were to 1) determine the effects of humic acid in growth medium contaminated with Cd and Pb on the absorption of Cd and phenol content in patchouli, and 2) determine the Cd tolerance level of the growth media. A completely randomized factorial design was used for the experiment with two factors. The heavy metals were a combination of pure PbNO3 and Cd (PC) with a ratio 1 : 1, and included five concentrations: PC0 (without PbNO3 and without Cd); PC1 (250 ppm PbNO3 + 250 ppm Cd); PC2 (500 ppm PbNO3 + 500 ppm Cd); PC3 (750 ppm PbNO3 + 750 ppm Cd); PC4 (1,000 ppm PbNO3 + 1,000 ppm Cd) and humic acid concentration (0; 6,000; 12,000; and 18,000 ppm). Each treatment was replicated three times. The parameters observed were plant biomass, Cd absorption, and phenol content. The application rate of humic acid to the plant medium containing heavy metals influenced the growth of patchouli, Cd absorption, and phenol content. An application rate of 12,000 ppm of humic acid reduced the toxicity of the heavy metals and increased the dry biomass and phenol content of patchouli

Hydrophilic and lipophilic radiopharmaceuticals as tracers in pharmaceutical development: In vitro – In vivo studies

BACKGROUND: Scintigraphic studies have been performed to assess the release, both in vitro and in vivo, of radiotracers from tablet formulations. Four different tracers with differing physicochemical characteristics have been evaluated to assess their suitability as models for drug delivery. METHODS: In-vitro disintegration and dissolution studies have been performed at pH 1, 4 and 7. In-vivo studies have been performed by scintigraphic imaging in healthy volunteers. Two hydrophilic tracers, ((99m)Tc-DTPA) and ((99m)Tc-MDP), and two lipophilic tracers, ((99m)Tc-ECD) and ((99m)Tc-MIBI), were used as drug models. RESULTS: Dissolution and disintegration profiles, differed depending on the drug model chosen. In vitro dissolution velocity constants indicated a probable retention of the radiotracer in the formulation. In vivo disintegration velocity constants showed important variability for each radiopharmaceutical. Pearson statistical test showed no correlation between in vitro drug release, and in vivo behaviour, for (99m)Tc-DTPA, (99m)Tc-ECD and (99m)Tc-MIBI. High correlation coefficients were found for (99m)Tc-MDP not only for in vitro dissolution and disintegration studies but also for in vivo scintigraphic studies. CONCLUSION: Scintigraphic studies have made a significant contribution to the development of drug delivery systems. It is essential, however, to choose the appropriate radiotracers as models of drug behaviour. This study has demonstrated significant differences in release patterns, depending on the model chosen. It is likely that each formulation would require the development of a specific model, rather than being able to use a generic drug model on the basis of its physicochemical characteristics

Analisis Rancangan Dasar Sistem Pgnaa Menggunakan Sumber Neutron dari Beamport Reaktor Kartini

ANALISIS RANCANGAN DASAR SISTEM PGNAA MENGGUNAKAN SUMBER NEUTRON DARI BEAMPORT REAKTOR KARTINI. Telah dilakukan perancangan dasar sistem PGNAA menggunakan salahsatu beamport reaktor Kartini sebagai sumber neutron. Moderator neutron ditempatkan pada ujung kolom berkas neutron untuk membuat berkas neutron menjadi termal. Berkas diarahkan menuju ruang sampel PGNAA dengan menggunakan kolimator yang berfungsi sebagai penyaring berkas neutron sejajar. Pada penggal kolimator yang berpotongan dengan jendela beamport dipasang neutron beam shutter untuk menutup berkas neutron apabila tidak digunakan untuk PGNAA. Beam stopper dipasang dibelakang ruang sampel PGNAA untuk menangkap berkas neutron yang lolos. Perhitungan sifat neutronik dilakukan untuk memilih bahan material yang memenuhi syarat fungsi sebagai sub-komponen PGNAA dan menentukan ukuran geometrinya. Dari hasil perhitungan diperoleh data bahan yang baik untuk moderator yaitu grafit, bahan kolimator adalah aluminium, bahan beam shutter dan beam stopper adalah komposit boraks-parafin. Panjang moderator 90 cm, panjang kolimator 173 cm dengan tetapan kolimasi D/L=0,015, tebal beam shutter dan beam stopper masing-masing 22 cm dan 30 cm. Dipasang perisai gamma dan perisai neutron untuk menutup berkas neutron keluar dari sela dinding dalam beamport dan didnding luar kolimator. Bahan perisai tersebut dibuat dari komposit boraks parafin 25% berat dan timbal yang masing-masing panjangnya 50 cm dan 30 cm. Hasil analisis menunjukkan bahwa dari fluks neutron awal pada beamport bagian dalam sebesar 1,5.1012 n/cm2s dapat menghasilkan fluks neutron termal di ruang sampel PGNAA 1,76.108 n/cm2s dengan arus neutron termal 9,29.108 n/s. Nilai fluks neutron termal tersebut memenuhi persyaratan untuk suatu sistem PGNAA yaitu berada pada orde 106 s/d 108 n/cm2s