Validation and improvement of gamma heating calculation methods for the G.A. Siwabessy multipurpose reactor

et al. 2023

Tri Dasa Mega

Nuclear fission reactions produce a lot of radionuclides that release energy, one of which is in the form of gamma radiation. Gamma radiation is produced by various types of radionuclides, and nuclear reactor fuel will produce different values of gamma intensity. Uranium Molybdenum (U7Mo-Al) is the type of nuclear fuel for future research reactors that possesses many advantages. For the application of molybdenum-based fuel, it is necessary to determine the resulting gamma radiation. The purpose is to determine the gamma radiation produced from molybdenum-based fuel with various densities. This study begins with the determination of the mass composition of the reactor component, calculations with ORIGEN2.1, and data output analysis. The U7Mo-Al density was varied, namely 2.96 gU/cm3, 3.85 gU/cm3, 4.44 gU/cm3, 5.43 gU/cm3, 6.91 gU/cm3, and 8.29 gU/cm3. The gamma radiation yield of U7Mo-Al is lower than that of uranium silicide (U3Si2) with the same density of 2.96 gU/cm3. The result will add to the justification for the superiority of U7Mo-Al compared to U3Si2/Al. For U7Mo-Al with densities of 3.85 gU/cm3, 4.44 gU/cm3, 5.43 gU/cm3, 6.91 gU/cm3, and 8.29 gU/cm3, the one that produced the lowest gamma radiation intensity is 3.85 gU/cm3 while the highest is 8.29 gU/cm3. This explains that the intensity of the gamma radiation produced is directly proportional to the fuel density. The low intensity of gamma radiation in molybdenum-based fuel can be used as a suggestion in shielding design to ensure the operational safety of reactors.

Section: Resultsmentioning

confidence: 99%

Determining Gamma Source in Uranium Molybdenum of Fuel in G.A Siwabessy Multi Purpose Reactor

Riskiana

Rohanda²,

et al. 2023

Tri Dasa Mega

“…The duration of irradiation to be used is eight days. The input data for the flux value of the CIP irradiation position on the reactor core was differentiated into U3Si2-Al (density 2.96 gU/cc) and U9Mo-Al (density 3.55 gU/cc), operated at a power of 15 MWt (shown in Table 3) [12,13]. The input data will then be entered into the listing of ORIGEN2.1 for each fuel.…”

Section: B Writing Program Input On Origen21mentioning

confidence: 99%

A Simulation of Irradiation Calculations on Lutetium-177 Production in RSG-Gas Using U3si2-Al and U9mo-Al Fuels

Rosmayani

Rohanda²,

2023

Tri Dasa Mega

This research is a simulation of irradiation calculations on the production of the radioisotope Lutetium-177 (177Lu) in the G.A Siwabessy Reactor (RSG-GAS). This study aims to analyze the comparative calculation of 177Lu activity and its purity. One of the production methods of 177Lu in RSG-GAS is carried out by irradiating Lu2O3 targets. This Lu2O3 target irradiation produced the radioisotope 177Lu along with 177mLu as an impurity. For Medical treatment using radioisotopes, the minimum activity for 177Lu is 20 GBq/mg, and the impurity should not exceed 0.1%. Calculations were carried out with thermal neutron flux input at 15 MWt operational power for the RSG-GAS core with U3Si2-Al fuel (density 2.96 gU/cc and 3.55 gU/cc) and U9Mo-Al fuel (density 3.55 gU/cc). Calculations were carried out by simulating 8 days of irradiation using ORIGEN2.1. The results showed that the 177Lu activity resulting from irradiation of Lu2O3 targets at various CIP positions in the U9Mo-Al reactor core was larger than that of the U3Si2-Al core. Until the 30th day, the 177Lu product resulting from irradiation on the U3Si2-Al and U9Mo-Al cores still meets the minimum value of 20 GBq/mg for treatment needs in nuclear medicine, with the activity value of 177Lu resulting from irradiation on the U3Si2-Al core ranging from 241-403 GBq/mg, while the activity of irradiated 177Lu in the U9Mo-Al core ranges from 335-561 GBq/mg. In addition, until the 30th day of decay, 177Lu has a percentage value of 177mLu irradiated in the U9Mo-Al and U3Si2-Al cores of 0.0346% and 0.0344%, respectively. The results are still below the maximum impurity value of 0.1% and thus safe to use as a therapeutic agent. Keywords: 177Lu, Activity, RSG-GAS, ORIGEN2, Irradiation

“…Penentuan panas gamma dapat langsung ditentukan dengan menginputkan emisi sinar gamma hasil perhitungan pada program Gamset. Keakuratan Gamset telah teruji baik dalam menghitung panas gamma pada RSG-GAS yaitu dalam penelitian setiyanto [5], [10], anis rohanda [11]- [12] dan Husnayani [13].…”

Section: Pendahuluanunclassified

ESTIMASI PANAS GAMMA PADA PRODUKSI RADIOISOTOP Lu-177, Ir-192, DAN Au-198 DI TERAS MOLIBDENUM RSG-GAS

Riskiana

Rohanda

2022

urania

ESTIMASI PANAS GAMMA PADA PRODUKSI RADIOISOTOP Lu-177, Ir-192, DAN Au-198 DI TERAS MOLIBDENUM RSG-GAS. Panas gamma (Gamma heating) merupakan isu penting terkait keselamatan fasilitas iradiasi suatu reaktor dan sampel iradiasinya. Panas gamma dihasilkan dari interaksi energi gamma dengan material target. Energi gamma yang dihasilkan dari reaktor memiliki karakteristik energi gamma yang berbeda yang salah satunya dipengaruhi oleh jenis bahan bakar (jenis teras). Uranium molibdenum (UMo) merupakan bahan bakar masa depan yang memiliki beberapa keunggulan dibandingkan uranium oksida (UO2) dan silisida (USi) salah satunya dapat meningkatkan operasi reaktor. Untuk itu dilakukan studi komputasi panas gamma RSG-GAS dengan bahan bakar UMo pada beberapa proses produksi radioisotop seperti radioisotop Lu-177, Ir-192, dan Au-198. Penelitian ini menggunakan code ORIGEN untuk menghitung energi gamma yang dihasilkan untuk jenis bahan bakar UMo. Estimasi panas gamma menggunakan program Gamset, suatu program didesain dan sudah teruji untuk menghitung panas gamma di RSG-GAS. Hasil perhitungan panas gamma berbahan bakar UMo di RSG-GAS dalam kisaran 4,85 W/g ~ 8,69 W/g . Hasil ini lebih kecil dibandingkan dengan panas gamma pada uranium silisida (USi) yaitu sekitar 9,27 W/g ~ 13,3 W/g. Radioisotop Lu-177 memiliki panas gamma terbesar sekitar 8,69 W/g, yang diikuti oleh Au-198 dan Ir-192 yang masing-masing sebesar 5,89 W/g dan 7,12 W/g. Panas gamma pada ketiga radioisotop yang diproduksi oleh RSG-GAS berbahan bakar UMo tidak melebihi panas gamma maksimum (20 W/g) yang telah ditentukan sehingga dapat diartikan aman untuk reaktor dan sampel.Kata kunci: Panas gamma, UMo, RSG-GAS, radioisotop