Article Per Year (5 Year)
p-Index From 2021 - 2026
0.23
P-Index
This Author published in this journals
All Journal Jurnal Forum Nuklir INDONESIAN JOURNAL OF URBAN AND ENVIRONMENTAL TECHNOLOGY
Sugeng Purnomo
Unknown Affiliation
Agriculture, Biological Sciences & Forestry Chemical Engineering, Chemistry & Bioengineering Civil Engineering, Building, Construction & Architecture Energy Environmental Science Materials Science & Nanotechnology

Published : 3 Documents Claim Missing Document
Claim Missing Document
Check
Articles

Found 3 Documents
Search

 1 
Proses Oksidasi Biokimia untuk Pengolahan Limbah Simulasi Cair Organik Radioaktif Gunandjar Gunandjar; Zainus Salimin; Sugeng Purnomo; Ratiko Ratiko
Jurnal Forum Nuklir JFN Vol 4 No 1 Mei 2010
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (333.737 KB) | DOI: 10.17146/jfn.2010.4.1.220

Abstract

Kegiatan industri nuklir menimbulkan limbah cair organik seperti limbah detergen dari pencucian pakaian kerja, pelarut 30% TBP (tri-n-butyl phosphate) dalam kerosen dari pemurnian ataupun pengambilan uranium dari gagalan fabrikasi elemen bahan bakar, pelarut yang mengandung D2EHPA (di-2-ethyl hexyl phosphoric acid) dan TOPO (trioctyl phospine oxide) dalam kerosin dari pemurnian asam fosfat. Limbah tersebut bersifat bahan berbahaya dan beracun (B-3) serta radioaktif, oleh karena itu limbah tersebut harus diolah sehingga terjadi detoksifikasi B-3 dan dekontaminasi radionuklidanya. Telah dilakukan penelitian proses oksidasi biokimia pengolahan limbah simulasi cair organik radioaktif dari pencucian pakaian kerja menggunakan campuran bakteri mutan aerob bacillus sp, pseudomonas sp, arthrobacter sp, dan aeromonas sp. Limbah berkadar deterjen 1,496 g/L, aktivitas 10-1Ci/m3, dengan COD (Chemical Oxygen Demand) 128, BOD (Biological Oxygen Demand) 68 dan TSS (Total Suspended Solid) 1000 ppm, diolah dengan oksidasi biokimia dengan penambahan bakteri yang diberi nutrisi nitrogen dan fosfor, dan diaerasi. Hasilnya menunjukkan bahwa bakteri mampu menguraikan detergen menjadi karbon dioksida dan air sehingga memenuhi baku mutu air golongan B dengan kadar BOD dan COD berturut-turut berharga 6 dan 0 ppm, diperlukan waktu penguraian 106 jam untuk pemenuhan baku mutu tersebut. Semakin lama waktu proses memberikan kadar padatan total dalam lumpur semakin besar karena biomassa yang terbentuk dari massa koloni bakteri yang hidup dan mati semakin banyak.
Cs-137 AND Co-60 CONCENTRATION REMOVAL ON RADIOACTIVE LIQUID WASTE BY ION EXCHANGE AND COAGULATION-FLOCCULATION METHOD Pinky Septria Adella; Asih Wijayanti; Dwi Indrawati; Sugeng Purnomo
INDONESIAN JOURNAL OF URBAN AND ENVIRONMENTAL TECHNOLOGY Volume 1, Number 1, October 2017
Publisher : Universitas Trisakti

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1082.459 KB) | DOI: 10.25105/urbanenvirotech.v1i1.2402

Abstract

Radioactive liquid waste is a hazardous and toxic waste which comes from nuclear research laboratory. This waste may cause explosion when treated with evaporator. Aim: This research was intended to reduce and determine the best removal method of Cs-137 and Co-60 from radioactive liquid waste. Methodology and Result: Methods used in this research are ion exchange and coagulation-flocculation method. In ion exchange method used two types of reactor that is continuous reactor and batch reactor with variables of debit, material type, mesh size and mass of material, while in coagulation-flocculation method used jar test with ferro sulfate coagulant dose variables. Continuous reactor consisting of separating funnel and chromatography column with a diameter of 4 cm and height 60 cm, whereas in batch reactor used jar test stirrer. The application of radioactive liquid waste treatment is done using selected method, with the start condition for Cs-137 of 3 x 10-5 mCi/L and for Co-60 of 4.8 x 10-6 mCi/L. Application of Ion Exchanger with Continuous Reactor Speed 60 mL/10 sec and Coagulation-Flocculation with dose of 100 mmol/L in pH 8 effluent result the value for Cs-137 and Co-60 that undetected or very little, below 10-6 mCi/L. Conclusion, significance and impact study: The conclusion of this study is suitable with the Government Regulation Number 10 of 1997 about nuclear power, the limit of quality standard for Cs-137 and Co-60 is below 10-6 mCi/L. So the appropriate method to treat of Cs-137 and Co-60 are Ion Exchanger with Continuous Reactor Speed 60 mL/10 sec and Coagulation-Flocculation with dose of 100 mmol/L in pH 8.
Cs-137 AND Co-60 CONCENTRATION REMOVAL ON RADIOACTIVE LIQUID WASTE BY ION EXCHANGE AND COAGULATION-FLOCCULATION METHOD Pinky Septria Adella; Asih Wijayanti; Dwi Indrawati; Sugeng Purnomo
INDONESIAN JOURNAL OF URBAN AND ENVIRONMENTAL TECHNOLOGY Volume 1, Number 1, October 2017
Publisher : Universitas Trisakti

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25105/urbanenvirotech.v1i1.2402

Abstract

Radioactive liquid waste is a hazardous and toxic waste which comes from nuclear research laboratory. This waste may cause explosion when treated with evaporator. Aim: This research was intended to reduce and determine the best removal method of Cs-137 and Co-60 from radioactive liquid waste. Methodology and Result: Methods used in this research are ion exchange and coagulation-flocculation method. In ion exchange method used two types of reactor that is continuous reactor and batch reactor with variables of debit, material type, mesh size and mass of material, while in coagulation-flocculation method used jar test with ferro sulfate coagulant dose variables. Continuous reactor consisting of separating funnel and chromatography column with a diameter of 4 cm and height 60 cm, whereas in batch reactor used jar test stirrer. The application of radioactive liquid waste treatment is done using selected method, with the start condition for Cs-137 of 3 x 10-5 mCi/L and for Co-60 of 4.8 x 10-6 mCi/L. Application of Ion Exchanger with Continuous Reactor Speed 60 mL/10 sec and Coagulation-Flocculation with dose of 100 mmol/L in pH 8 effluent result the value for Cs-137 and Co-60 that undetected or very little, below 10-6 mCi/L. Conclusion, significance and impact study: The conclusion of this study is suitable with the Government Regulation Number 10 of 1997 about nuclear power, the limit of quality standard for Cs-137 and Co-60 is below 10-6 mCi/L. So the appropriate method to treat of Cs-137 and Co-60 are Ion Exchanger with Continuous Reactor Speed 60 mL/10 sec and Coagulation-Flocculation with dose of 100 mmol/L in pH 8.
Co-Authors Asih Wijayanti Dwi Indrawati Endang Listyaningsih S Gunandjar Gunandjar Lilik Wijayanti Pinky Septria Adella Ratiko Ratiko Sigit Setyawan Siti Marufah Sri Haryati Widia Susanti Yulia Sari Zainus Salimin