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All Journal Jurnal Forum Nuklir Ganendra: Majalah IPTEK Nuklir Berkala Arkeologi Berkala Arkeologi Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir

Kris Tri Basuki

Unknown Affiliation

Author-ID : 432083

Computer Science & IT Earth & Planetary Sciences Materials Science & Nanotechnology Social Sciences Other

Published : 8 Documents Claim Missing Document

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Articles

PERANCANGAN REAKTOR BATCH UNTUK PEMISAHAN PERAK DARI LARUTAN BEKAS PENCUCIAN FILM RADIOGRAFI Salman Yasir Fakhri Putra; Noor Anis Kundari; Kris Tri Basuki
Jurnal Forum Nuklir JFN Vol 10 No 2 November 2016
Publisher : BATAN

PERANCANGAN REAKTOR BATCH UNTUK PEMISAHAN PERAK DARI LARUTAN BEKAS PENCUCIAN FILM RADIOGRAFI. Penelitian ini dilakukan untuk menentukan kinetika proses pelarutan dan desain reaktor batch. Fixer bekas menjadi masalah dikarenakan pada fixer bekas mengandung logam Ag yang termasuk logam berat dan digolongkan limbah B3.Namun selain fixer bekas tergolong dalam limbah B3, logam Ag yang terkandung pada fixer bekas juga mempunyai nilai ekonomis karena tergolong logam mulia. Oleh karena itu, dilakukan perancangan reakotr batch untuk untuk mengurangi masalah limbah di lingkungan. Metode untuk menentukan konstanta kinetika pada proses pelarutan adalah melarutkan Ag2S dan HNO3, diaduk dan dipanaskan pada suhu 90OC konstan dengan memvariasikan waktu pengadukan. Nilai konstanta kinetika proses Pelarutan Adalah 0,216/menit. Berdasarkannilai konstanta knetika yang diperoleh, dapat dihitung rancangan reaktor batch pada proses pertukaran logam untuk kapasitas 99 L/bulan sebesar D = 45 cm, H = 68cm, t = 0,35 cm, P = 0,76watt, dan pada proses pelarutan adalah D = 44 cm, H = 66cm, t = 0,33 cm, P =42,29watt.

PEMISAHAN Ce DAN Nd MENGGUNAKAN RESIN DOWEX 50W-X8 MELALUI PROSES PERTUKARAN ION Dwi Biyantoro; Kris Tri Basuki; Muhadi Ayub Washito
GANENDRA Majalah IPTEK Nuklir Volume 9 Nomor 1 Januari 2006
Publisher : Website

PEMISAHAN Ce DAN Nd MENGGUNAKAN RESIN DOWEX 50W-X8 MELALUI PROSES PERTUKARAN ION.Telah dilakukan penelitian pemisahan Ce dan Nd menggunakan kolom penukar ion yang berisi resin Dowex 50W-X8ukuran 100 – 200 mesh dan eluen EDTA. Penelitian ini bertujuan untuk mengetahui keberhasilan proses pemisahanCe dan Nd menggunakan kolom penukar ion. Pemisahan ini dilakukan dengan menggunakan kolom gelasberdiameter 0,4 cm, panjang 95 cm, umpan campuran Ce dan Nd pada pada kecepatan alir EDTA 0,05 ml/menit. Eluatditampung secara fraksional setiap 5 ml kemudian dianalisis menggunakan spektrometer pendar sinar-X. Dari hasilpenelitian diperoleh nilai kapasitas resin Dowex 50W-X8 = 5,28 mgrek/g, resolusi Ce-Nd = 1,47, dan faktor pemisahanCe-Nd = 5,16 pada perbandingan umpan Ce dan Nd = 20 : 1.

STUDI OPERASI RESIN PENUKAR ION DALAM SISTEM PURIFIKASI AIR PRIMER PWR Dwi Biyantoro; Kris Tri Basuki; Subagiono Subagiono
GANENDRA Majalah IPTEK Nuklir Volume 9 Nomor 1 Januari 2006
Publisher : Website

STUDI OPERASI RESIN PENUKAR ION DALAM SISTEM PURIFIKASI AIR PRIMER PWR. Telah dilakukan studioperasi resin penukar ion dalam sistem purifikasi air primer PWR. Air pendingin reaktor yang pada awalnya sesuaidengan persyaratan setelah pengoperasian reaktor sering kualitasnya berubah, sehingga harus dimurnikan. Unsurunsurpengotor dalam air primer PWR diidentifikasi sebagai penyebab pengotor seperti korosi, pelepasan produk fisi(Cs137, Sr90, Co60,C14, Tc99), dan pelepasan kembali unsur oleh resin penukar ion. Air yang sudah tidak sesuai denganpersyaratan reaktor kemudian dilakukan pemurnian mengunakan resin penukar ion. Resin-resin ini digunakan untukmenghilangkan kotoran yang tidak diinginkan, seperti material-material radioaktif atau pencemaran yang lain yangdapat secara potensial merugikan peralatan atau merusak bahan bakar reaktor. Resin-resin penukar ion yangdirekomendasikan digunakan dalam reaktor PWR (komersial) untuk purifikasi adalah sebagai berikut: penukarpenukarkation : Resin IRC-50, Resin 200-H, dan Resin 650-C, penukar-penukar anion : Resin A-550 dan Resin 900-OH, dan penukar campuran : Resin 21H (ECODEX P-202-H). Resin penukar ion tersebut adalah termasuk polimerorganik sintetis yang mempunyai matriks/network yang berupa polistiren (PS) dan pengikat silangnya divinil benzen(DVB). Resin polistiren – divinilbenzen (PSDVB) mempunyai sifat-sifat yang menguntungkan sebagai penukar ionseperti kapasitas penukaran yang baik, selektif, ukuran partikel dengan ukuran tertentu, kestabilan resin tinggi padaberbagai pH, laju pertukaran ion yang cepat, dan limbah yang dihasilkan relatif kecil.

Peranan Teknologi Nuklir Di Bidang Arkeologi Indonesia Dan Pengembangannya Faisal Wisjachudin; F. Lahagu; Djoko Widodo; Kris Tri Basuki; A. Taftazani; Suci Widayati
Berkala Arkeologi Vol 20 No 1 (2000)
Publisher : Balai Arkeologi Yogyakarta

Hasil analisis menunjukkan bahwa peranan teknik nuklir untuk cuplikan arkeologi sangat bermanfaat dan perlu dikembangkan dan dilakukan oleh para ahli umumnya, khususnya bidang arkeologi. Seperti diketahui bahwa analisis dengan metode analisis kimia biasa, mempunyai beberapa kelemahan antara lain belum bisa menganalisis unsur-unsur tertentu, membutuhkan cuplikan yang cukup banyak karena analisisnya untuk satu unsur dibutuhkan satu cuplikan. Sedangkan analisis dengan Pertanggalan relatif yang selama ini dilakukan oleh para ahli arkeologi, akan lebih akurat apabila diikuti dengan pertanggalan absolut.

PERANAN TEKNOLOGI NUKLIR DI BIDANG ARKEOLOGI INDONESIA DAN PENGEMBANGANNYA Faisal Wisjachudin; F. Lahagu; Djoko Widodo; Kris Tri Basuki; A. Taftazani; Suci Widayati
Berkala Arkeologi Vol. 20 No. 1 (2000)
Publisher : BRIN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.30883/jba.v20i1.813

The results of the analysis show that the role of nuclear engineering for archaeological evidence is very useful and needs to be developed and carried out by experts in general, especially in the field of archaeology. As it is known that the analysis using the ordinary chemical analysis method has several weaknesses, including not being able to analyze certain elements, requiring quite a lot of samples because the analysis for one element requires one sample. Meanwhile, the analysis using the relative dating that has been done by archaeologists will be more accurate if it is followed by absolute dating.

ADSORPTION OF URANIUM SIMULATION WASTE USING BENTONITE: TITANIUM DIOXIDE Kris Tri Basuki; Lutfi Aditya Hasnowo; Elza Jamayanti
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 1 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2019.25.1.4527

Bentonite is a clay material of high surface area that have galleries within its structure. Bentonite that is modified with TiO2 will have high adsorption capability. In this study, natural bentonite and bentonite: TiO2 were characterized with FTIR, XRD and BET instruments to determine functional group, basal spacing, and specific surface area. This study also investigates the adsorption of bentonite:TiO2 in various environmental factors, such as pH (pH 1, 3, 5, and 8), contact time (10, 20, 30, 40, 50, 60, 70, 90, and 120 min), and initial uranium concentration (20, 40, 60, 80 ppm), and their influences on adsorption capacity, and determine the kinetics equation and adsorption isotherm. Based on FTIR analysis, a decrease in the band of O-H bond from water molecule was observed, which indicates the presence of TiO2 in bentonite interlayer structure. The XRD characterization of bentonite: TiO2 does not show diffraction peak in 001 plane. This is due to delamination of bentonite interlayer structure. Delamination is caused by the presence of TiO2 in large quantities, thus damaging the bentonite interlayer structure into irregular sheets. Bentonite as sheets will cause the basal spacing to increase and it is anticipated that XRD will find it difficult in detecting the 001 plane at a low 2 theta angle. The surface area of bentonite: TiO2 has increased by 12.04 m2/g. The maximum adsorption capacity of U(VI) took place at pH 5.0 for 70 minutes contact time and uranium concentration of 60 ppm. In this study, the adsorption kinetic and adsorption isotherm are pseudo second-order kinetic and Langmuir isotherm. The kinetic constant and maximum adsorption capacity of bentonite: TiO2 are 0.075 g/mg.min and 5.848 mg/g respectively.

EFFECT OF CURRENT, TIME, TYPE OF FEED AND CATHODE ON ELECTROPLATING PROCESS OF URANIUM SOLUTION Sigit; Ghoib Widodo; Bangun Wasito; Kris Tri Basuki; Fahrunissa
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.1.3155

Electroplating of uranyl nitrate and process effluent has been carried out in order to collect uranium contained therein using Pt/Pt and Pt/SS electrodes at various current and time values. The materials used as electrode were Pt (platinum) and SS (Stainless Steel). Feed solution of 250 mL was entered into a beaker glass equipped with Pt anode - Pt cathode or Pt anode - SS cathode and connected to direct current source from DC power supply at various current values and for various time periods so that uranium precipitated and deposited onto the cathode. Upon deposition completion, the cathode was removed and weighed to determine weight of precipitates, while the solution was analyzed to determine uranium concentration decrease after electroplating process. The experiment shows that a relatively good time to acquire uranium deposit at the cathode was 1 hour at 7 amperes, with uranyl nitrate as feed and Pt (platinum) as cathode. In these conditions, uranium deposit attached to the cathode amounted to 74.96% of the original weight of uranium oxide in the feed or 206.5 mg by weight. The use of Pt cathode for uranyl nitrate feed, and SS and Pt cathodes for effluent feed resulted in uranium specific weight at the cathode of 12.99 mg/cm2, 2.4 mg/cm2 and 5.37 mg/cm2 respectively for 7 Ampere current for 1 hour electroplating time.

USE OF MEMBRANE EMULSION SPAN 80 AND TOPO IN URANIUM EXTRACTION AND STRIPPING Kris Tri Basuki; Nurimaniwathy; Dian Puspita; Bambang E.H.B
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2016.22.3.3185

Membrane emulsion span 80 and TOPO used in uranium extraction and stripping has been done. The extraction was carried outby emulsion membrane H3PO4 in TOPO-Kerosene. The feed or external aqueous phase was uranium in HNO3. The emulgator span-80 was used to obtain a stable emulsion membrane system. The influence factors were percentage of TOPO-Kerosene, time extraction, molarity of external aqueous phase and molarity of internal aqueous. After the emulsion membrane was formed, the extraction and stripping process was performed. The ratio volume feed: volume membrane phase equal to 1 : 1 and volume of 5 % TOPO-Kerosene: Volume 3 M H3PO4 equal 1 : 1 were used. The relatively good yield were obtained at concentration of TOPO in Kerosene and 3 M H3PO4 was 5 %, molarity of internal aqueous phase equal to 1 M, molarity of external aqueous phase 3 M H3PO4 and time extraction equal to 10 minutes with the speed of emulsification was 8000 rpm. At this condition the extraction efficiency of uranium obtained was 97.8 %, the stripping efficiency 52.56 %, and the total efficiency was 53.80 %.

Co-Authors A. Taftazani Bambang E.H.B Bangun Wasito Dian Puspita Djoko Widodo Dwi Biyantoro Elza Jamayanti F. Lahagu Fahrunissa Faisal Wisjachudin Ghoib Widodo Lutfi Aditya Hasnowo Muhadi Ayub Washito Noor Anis Kundari Nurimaniwathy Salman Yasir Fakhri Putra Sigit Subagiono Subagiono Suci Widayati

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