STUDI PRODUKSI RADIONUKLIDA MEDIS UNTUK GENERATOR 89Sr/90Y DARI HASIL REAKSI 89Rb(p,n)89Sr/90Y PADA SIKLOTRON MEDIK SECARA KOMPUTASI

Yusup Hidayat; Asep Yoyo Wardaya; Pandji Triadyaksa; Evi Setiawati; Zaenul Muhlisin; Sumariyah Sumariyah; Jatmiko Endro Suseno; Qidir Maulana Binu Soesanto

STUDI PRODUKSI RADIONUKLIDA MEDIS UNTUK GENERATOR 89Sr/90Y DARI HASIL REAKSI 89Rb(p,n)89Sr/90Y PADA SIKLOTRON MEDIK SECARA KOMPUTASI

*Yusup Hidayat - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Asep Yoyo Wardaya - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Pandji Triadyaksa - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Evi Setiawati - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Zaenul Muhlisin - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Sumariyah Sumariyah - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Jatmiko Endro Suseno - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

Qidir Maulana Binu Soesanto - Departemen Fisika, Fakultas Sains dan Matematika, Universitas Diponegoro, Semarang, Indonesia

BibTex Citation Data :

@article{BFIS27310,
    author = {Yusup Hidayat and Asep Wardaya and Pandji Triadyaksa and Evi Setiawati and Zaenul Muhlisin and Sumariyah Sumariyah and Jatmiko Suseno and Qidir Binu Soesanto},
    title = {STUDI PRODUKSI RADIONUKLIDA MEDIS UNTUK GENERATOR 89Sr/90Y DARI HASIL REAKSI 89Rb(p,n)89Sr/90Y PADA SIKLOTRON MEDIK SECARA KOMPUTASI},
    journal = {BERKALA FISIKA},
  volume = {22},
    number = {4},
    year = {2019},
    keywords = {medical cyclotron, calculation and modeling, 90Y activity},
    abstract = { A computational calculation to determine production capacity of   90  Y   from the results of nuclear reactions   89  Rb(p,n)  89  Sr/  90  Y   from several medical cyclotrons has been carried out  .   Calculations were used to obtain the target thickness of   89  Rb   and maximum activity of   90  Y   on variable energy, time and irradiation currents. Calculations were also carried out to measure the impurity radionuclide activity during the reaction. The results activities of   90  Y   were obtained through modeling using the SRIM-2013 software and the TENDL-2017 application and calculated using MATLAB software. The results modeling and of calculations can predict the activity of   90  Y   and it can be used as an initial reference in the radionuclide production process using a cyclotron. The maximum activity of   90  Y   of 5409.80 mCi with a 10.54 mm-target thickness of   89  Rb   is generated from a cyclotron which has a 30 MeV proton beam with a 50 μA radiation current beam and 2 hours irradiation time. Using the same proton, current and irradiation time at irradiation energy of 8 MeV, 15 MeV and 22 MeV, the produced activity of   90  Y   was smaller, there are 552.28 mCi, 2100.39 mCi and 3644.31 mCi. The radioisotope of   90  Y can be used   in patients with a normal dose of 0.4 mCi / kg body weight, therefore in one production can supply the needs of 104 patients.   Keywords:   medical cyclotron, calculation and modeling,   90  Y activity },
   pages = {153--160}    url = {https://ejournal.undip.ac.id/index.php/berkala_fisika/article/view/27310}
}

Citation Format:

Abstract

A computational calculation to determine production capacity of 90Y from the results of nuclear
reactions 89Rb(p,n)89Sr/90Y from several medical cyclotrons has been carried out. Calculations were used to obtain the target thickness of 89Rb and maximum activity of 90Y on variable energy, time and irradiation currents. Calculations were also carried out to measure the impurity radionuclide activity during the reaction. The results activities of 90Y were obtained through modeling using the SRIM-2013 software and the TENDL-2017 application and calculated using MATLAB software. The results modeling and of calculations can predict the activity of 90Y and it can be used as an initial reference in the radionuclide production process using a cyclotron. The maximum activity of 90Y of 5409.80 mCi with a 10.54 mm-target thickness of 89Rb is generated from a cyclotron which has a 30 MeV proton beam with a 50 μA radiation current beam and 2 hours irradiation time. Using the same proton, current and irradiation time at irradiation energy of 8 MeV, 15 MeV and 22 MeV, the produced activity of 90Y was smaller, there are 552.28 mCi, 2100.39 mCi and 3644.31 mCi. The radioisotope of 90Y can be used in patients with a normal dose of 0.4 mCi / kg body weight, therefore in one production can supply the needs of 104 patients.
Keywords: medical cyclotron, calculation and modeling, 90Y activity

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Keywords: medical cyclotron, calculation and modeling, 90Y activity

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Section: Articles

Language : EN

In Vol 22, No 4 (2019): Berkala Fisika Vol. 22 No. 4 Tahun 2019