Article Per Year (5 Year)
p-Index From 2020 - 2025
0
P-Index
This Author published in this journals
All Journal Jurnal Radioisotop dan Radiofarmaka Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir JKPK (Jurnal Kimia dan Pendidikan Kimia) Jurnal Kefarmasian Indonesia
Chairuman Chairuman
Pusat Radioisotop dan Radiofarmaka-BATAN, Serpong
Chemical Engineering, Chemistry & Bioengineering Chemistry Materials Science & Nanotechnology Medicine & Pharmacology

Published : 4 Documents Claim Missing Document
Claim Missing Document
Check
Articles

Found 4 Documents
Search

 1 
PEMBUATAN RADIOFARMAKA PET 18F_FDG MENGGUNAKAN MODUL SINTESA OTOMATIK Purwoko, Purwoko; Chairuman, Chairuman; Gunawan, Adang Hardi; Tahyan, Yayan; Lestari, Eny; Lestiyowati, Sri Aguswarini; Karyadi, Karyadi; Bagiawati, Sri
Jurnal Radioisotop dan Radiofarmaka Vol 13, No 2 (2010): Jurnal PRR 2010
Publisher : Jurnal Radioisotop dan Radiofarmaka

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

Abstract

ABSTRAKPEMBUATAN RADIOFARMAKA PET 18F_FDG MENGGUNAKAN MODUL SINTESAOTOMATIK.Radiofarmaka 2-(18F)Fluoro-2-deoksi-O-glukosa at au ISF(FOG) adalah radiofarmaka PET(Positron Emission Tomography) yang sangat penting untuk pencitraan lesi tumor. Oengan teknik PETmetabolisme glukosa dalam jaringan tumor di dalam tubuh dapat dibedakan dan diukur secara kuantitatifsehingga digunakan untuk diagnosa tingkat keganasan serta pemantauan pengobatan penyakit tumor ataukanker dalam bidang onkologi kedokteran. Telah dilakukan uji coba produksi 2-(lSF)Floro-2-deoksi-OglukosaISF_ FOG menggunakan perangkat modul sintesa otomatik TRACERlab MX. Perangkat modul inimemberikan kemudahan dalam sintesa rutin radiofarmaka lsF_FOG yang didasarkan pad a reaksi tlorinasinukleofilik terhadap prekursor manosa tritlat dengan katalisator kriptofik. Perolehan yield radiokimia lSF(FOG) mencapai 53,895% (tanpa koreksi waktu peluruhan) dalam waktu 40 men it, produk berupa larutanjernih tak berwarna pH : 6, steril dan bebas pirogen, kadar pengotor kriptofix sangat rendah dan kemurnianradiokimia 99,595 %.Kata kunci: PET, radiofarmaka,PRODUCTION OF PET RADIOPHARMACEUTICAL 18F_FDG USING SYNTHESIZERAUTOMATIC MODUL.Radiopharmaceutical 2-esF)Fluoro-2-0eoxy-O-Glukose or IsF(FOG) is animportant PET (Positron Emission Tomography) radiopharmaceutical for tumour imaging. In the PETtechnique glucose metabolism in tumour tissues can be determined quantitatively and used for diagnosisstaging and monitoring of treatment tumour or cancer disease in medical oncology. The production of 2eSF)Fluoro-2-0eoxy-O-Glucose ISF -FOG using compact automated system module TRACERlab MXhas been carried out. The modular setup of the apparatus permits reliable for routine synthesis ofradiopharmaceuticals lSF -FOG based on kriptofix mediated nucleophilic tluorination to mannose tritlateprecursor. Radiochemical yield of IsF-FOG was 53.895 % (decay time uncorrected) in 40 minutes. Theproduct showed that the colorless and clear solution at pH:6, sterile and pirogen free, kriptofix impuritieswas low and radiochemical purity was 99.595%.Keywords: PET, radiopharmaceutical, FOG
INFLUENCE OF CONTACT TIME ON LOADING 99MO(N,γ) WITH ALUMINA COLUMN IN 99MO / 99MTC GENERATOR Sulaiman, Sulaiman; Sugiharto, Yono; Setiawan, Gatot; Chairuman, Chairuman; H.G., Adang
JKPK (Jurnal Kimia dan Pendidikan Kimia) Vol 4, No 3 (2019): JKPK (Jurnal Kimia dan Pendidikan Kimia)
Publisher : Program Studi Pendidikan Kimia FKIP Universitas Sebelas Maret

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (858.614 KB) | DOI: 10.20961/jkpk.v4i3.29840

Abstract

Alumina is usually used for 99Mo absorbers obtained from 235U fission product because the use of 235U is getting limited, and as an alternative 99Mo obtained from natural MoO3 irradiation was used. The problem is that 99Mo produced was not carrier-free as 99Mo from 235U fission product because not all MoO3 is activated to 99Mo, then it is necessary to know the effect of contact time when loading 99Mo into the alumina column. To find out the effect of contact time, the experiment was carried out using 99Mo pH 4, acid alumina column, contact time was varied between 1 to 60 minutes with interval of 15 minutes, and the column was eluted using 2 kinds of eluent namely 0.9% NaCl and MEK. The elution of 99Mo/99mTc generator is performed 3 times, days 1, 2 and 3. The results showed that the performance of alumina in absorbing 99Mo influenced by time. The optimal contact time is 15 minutes for 0.9% NaCl solution and 45 minutes for MEK. The amount of 99Mo breakthrough (µCi99Mo/mCi99mTc) from the alumina column increases with elution time both using 0.9% NaCl or MEK. The 99mTc eluate obtained from this study does not meet standard requirements. The use of a tandem column is needed to prevent 99Mo breakthrough on the 99Mo/99mTc generator to get the 99mTc which meet standard requirement.
OPTIMASI pH ALUMINA dan 99Mo DALAM PEMBUATAN GENERATOR 99Mo/99mTc BERBASIS MoO3 ALAM Sulaiman, Sulaiman; Sugiharto, Yono; Chairuman, Chairuman; Setiawan, Gatot; Gunawan, Adang Hardi
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 24, No 2 (2018): Juni, 2018
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2018.24.2.4159

Abstract

OPTIMASI pH ALUMINA dan 99Mo DALAM PEMBUATAN GENERATOR 99Mo/99mTc BERBASIS MoO3 ALAM. Alumina sebagai bahan penyerap telah lama digunakan untuk radioisotop 99Mo pada generator 99Mo/99mTc penghasil 99mTc yang banyak digunakan di kedokteran nuklir untuk keperluan diagnosa. Selama ini alumina digunakan untuk penyerapan 99Mo yang diperoleh dari bahan fisi 235U. Adanya pembatasan penggunaan matriks bahan fisi 235U maka alternatif lain untuk memperoleh 99Mo dengan menggunakan MoO3 alam yang diiradiasi di reaktor nuklir. Radioisotop 99Mo yang dihasilkan dari reaksi ini memiliki sifat tidak bebas pengemban sebagaimana halnya 99Mo dari hasil fisi, karena tidak semua MoO3 yang diiradiasi teraktivasi menjadi 99Mo. Pada aplikasi generator 99Mo/99mTc berbasis MoO3 alam dengan menggunakan kolom alumina, perlu diketahui pH alumina yang optimal dalam penyerapan 99Mo, dan juga pH 99Mo. Pada penelitian ini digunakan tiga variasi kolom generator berbasis alumina yaitu alumina asam, alumina netral, dan alumina basa. Bahan matriks 99Mo juga dilakukan tiga variasi pH yaitu larutan 99Mo dengan pH 4, larutan 99Mo dengan pH 7, dan larutan 99Mo dengan pH 8. Generator dielusi dengan larutan salin dan diamati setiap hari selama 3 hari dan diteruskan setelah dua hari berikutnya selama 2 hari. Penyerapan 99Mo dari MoO3 alam oleh material alumina memberikan hasil penyerapan terbaik pada penggunaan alumina asam dengan larutan 99Mo pada pH 4. Dari ketiga variasi pH larutan Mo yang memberikan yield 99mTc terbaik adalah pada penggunaan larutan 99Mo dengan pH 4. Kolom yang memberikan 99Mo breakthrough terkecil adalah di kolom alumina asam terutama menggunakan larutan 99Mo dengan pH 4. Dengan demikian, untuk menyerapkan 99Mo dari Mo alam dapat digunakan alumina asam dengan menggunakan larutan 99Mo pada pH 4..Kata kunci: 99Mo, alumina, kolom, pH, yield.
Uji Klirens dan Uji Pirogenitas sebagai Bagian dari Penentuan Mutu Biologi Sediaan 90Y-EDTMP Sulaiman, Sulaiman; Aguswarini, Sri; Karyadi, Karyadi; Chairuman, Chairuman; Setiawan, Gatot; HG, Adang; Subur, M.
Jurnal Kefarmasian Indonesia VOLUME 8, NOMOR 2, AGUSTUS 2018
Publisher : Pusat Penelitian dan Pengembangan Biomedis dan Teknologi Dasar Kesehatan

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22435/jki.v8i2.352

Abstract

Cancer is one of the causes of death in Indonesia and even the world. Nuclear medicine techniques with radiopharmaceuticals and SPECT are one of the ways to treat cancer, but their use in Indonesia is not yet popular. Radiopharmaceuticals marked with radionuclide emitting beta (β) radiation are proven to be used for cancer therapy, one that has been developed in PTRR-BATAN is 90Y-EDTMP. Yttrium-90 is used in nuclear medicine by utilizing β radiation (E max 2.28 MeV). The β energy which is produced from the decay process of 90Y radionuclides to 90Zr can kill cancer cells. This study aimed to provide information about the substances biological effects so that preventive measures can be taken to protect humans. This study conducted evaluation of the 90Y-marked radiopharmaceutical (90Y produced from a 90Sr / 90Y generator which is 90Y-EDTMP) encompasses clearance test, pyrogen test, and dose safety test in experimental animals. The clearance test utilized mice, the pyrogen test utilized rabbits, and the dose safety test utilized mice. The results of the clearance test showed that 90Y-EDTMP compound which was excreted in 192 hour was 49.70% through urine and 14.59% through feces. The total excretion of 90Y-EDTMP within 192 hours was 64.57%. Based on the results of clearance tests with calculations, 90Y of 90Sr / 90Y generators in 90Y-EDTMP dosage form had 84.2 hours of half-life, 36.5 hours of an effective half-life and 52.7 hours of a residence time. Pyrogen test results showed pyrogen-free. The 90Y-EDTMP dose safety test showed that the dose is safe and not deadly. The development of 90Y-EDTMP is expected to be improved to produce radiopharmaceuticals for cancer therapy in order to make a real contribution in public health services.
Co-Authors Adang Hardi Gunawan Adang HG Eny Lestari Gatot Setiawan, Gatot H.G., Adang Karyadi Karyadi Purwoko Purwoko Sri Aguswarini Sri Aguswarini Lestiyowati Sri Bagiawati Subur, M. Sugiharto, Yono Sulaiman Sulaiman Yayan Tahyan