Claim Missing Document
Check
Articles

Found 2 Documents
Search

Imobilisasi Limbah Radioaktif Uranium Menggunakan Abu Batubara Sebagai Bahan Matriks Synroc Gunandjar Gunandjar
Prosiding Seminar Nasional Teknik Kimia "Kejuangan" 2015: Prosiding SNTKK 2015
Publisher : Seminar Nasional Teknik Kimia Kejuangan

Show Abstract | Download Original | Original Source | Check in Google Scholar

Abstract

The Immobilization of Uranium Radioactive Waste Using Coal-Ash as Matrix Material of Synroc. The decommissioning of Phosphoric Acid Purification Facility – Petro Chemical of Gresik (PAPF-PCG) generates radioactive liquid waste containing uranium. The waste was treated by bio-oxidation process using bacteria for volume reduction of the waste to become radioactive sludge waste. The sludge waste contains uranium is included the classification of long-life alpha radioactive waste. The sludge waste must be immobilized by solidification process for preparation of disposal to ensure the safety of the environment in the present and future. In this research aim to immobilization of the radioactive sludge waste by solidification using coal-ash as matrix material of titanate synroc. Immobilization process was carried-out by mix the radioactive sludge waste with coal-ash and precursor oxides namely BaO, CaO, and TiO2 as addition of matrix materials. The composition of matrix material of synroc using coal-ash and addition of precursor oxides (in weight %) i.e : Al2O3 (6.26); BaO (5.33); CaO (10.52); TiO2 (68.02) ; and SiO2 (6.07). Beside that the matrix material contains oxides minor (in weight %) i.e : Fe2O3 (3.48), MnO2 (0.04), K2O (0.20) and Na2O (0.08). Waste loading in the waste synroc block was 30 weight %. The mixture then was dried at temperature of 130 oC, and calcined at 750 oC. The powder of calcination result then was pressed in the molder. Furthermore, the sintering process was carried out at the temperature of 900 – 1300 o C for 3 hours to form the solid multiphase ceramic of synroc block. As a comparison was done immobilization process using matrix material of standard synroc. The quality of the synroc block produced from immobilization was determined by testing of density, compressive strength, and leach-rate ((the accelerated leach-rate at temperature of water 100 oC)). The test results showed that the best quality of waste synroc block was obtained at the sintering temperature of 1100 oC for 3 hours with values of density 2.28 g/cm3, compressive strength 5.57 kN/cm2, and leach-rate of uranium is 1.05x10-6 g.cm-2.day-1. This leach-rate of uranium is lower than the standar waste synroc block 1.17x10-5 g.cm-2.day-1. The quality of the waste synroc block produced by sintering process has fulfill the recommendation of IAEA.
IMOBILISASI LIMBAH RADIOAKTIF MENGANDUNG THORIUM MENGGUNAKAN BAHAN MATRIKS SYNROC Hasmaniar Septiani; Gunandjar Gunandjar; Mochtar Hadiwidodo
Jurnal Teknik Lingkungan Vol 2, No 4 (2013): Jurnal Teknik Lingkungan
Publisher : Departemen Teknik Lingkungan Fakultas Teknik Universitas Diponegoro

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (387.138 KB)

Abstract

Thorium waste generated from mantles factories in the form of sludge with a high water content that is derived from thorium-contaminated soil. This waste includes low activity radioactive waste of long-life alpha emitter that is harmful to humans and the environment. Based on these conditions, the immobilization process is required to confine the content of thorium. This research will develop thorium waste volume reduction by adsorption process using H-Zeolite made from Zeolite of  Lampung and imobilization process using synroc matrix material. This research emphasized the immobilization process to obtain waste synroc block with the best quality by studying the effect of sintering temperature and sintering time as well as the effect of waste loading in the formation process of  waste synroc block. The optimum condition is achieved at the waste loading 50% with the sintering temperature of 1250 ˚ C for 3 hours.