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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Ganendra: Majalah IPTEK Nuklir Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Tagor Malem Sembiring
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Biochemistry, Genetics & Molecular Biology Computer Science & IT Energy Environmental Science Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology Physics Other

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EVALUATION OF EQUILIBRIUM CORE OPERATION OF THE RSG-GAS REACTOR Iman Kuntoro; Surian Pinem; Tagor Malem Sembiring; Dwi Haryanto; Sigit Purwanto
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 23, No 1 (2021): FEBRUARY 2021
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2021.23.1.6150

Abstract

The Indonesian Multipurpose Reactor, RSG-GAS reactor will accomplish its first lifetime in December 2020. The reactor has been operated in safe and reliable manner for about 33 years since it commenced in operation in 1987 to serve radioisotopes production, NAA, neutron beam experiments, material irradiation, and reactor physics experimental activities as well as training. The paper is intended to evaluate its in-core fuel management that is the conformance between the theory and implementation of the equilibrium core. Evaluation of the reactor operation parameter was carried out for core numbers 91 – 100. The data show that excess reactivity, shutdown reactivity and control rod reactivity have no significant difference at each core. The result shows that the BATAN-FUEL accurately determine the equilibrium core and its fuel loading pattern.This in-core fuel management of the RSG-GAS reactor supports the safety of reactor operation.
NEUTRONIC ANALYSIS ON IRRADIATION OF THE LEU ELECTROPLATING TARGET IN THE RSG-GAS REACTOR FOR PRODUCTION OF 99MO RADIONUCLIDE Surian Pinem; Tagor Malem Sembiring; Tukiran Tukiran; Iman Kuntoro
GANENDRA Majalah IPTEK Nuklir Volume 21 Nomor 2 Juli 2018
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (429.215 KB) | DOI: 10.17146/gnd.2018.21.2.4392

Abstract

RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research material testing, industry demand, R & D institutions and universities. One of the routine activities performed for RSG-GAS reactor operation is irradiation of LEU targets into the core to produce 99Mo radionuclide. The target insertion in the core will change the neutronic characteristic of the core so it can exceed the safety limits of reactor operation. This paper analyzes the neutronic parameters due to the insertion of the LEU electroplating target into the reactor core irradiation facility. The neutronic parameters for optimizing the LEU electroplating irradiated target are important for the safety of the reactor operation. Neutronic parameter calculations were performed using WIMS/D5 and Batan-3DIFF codes routinely used for RSG-GAS core calculations. Based on calculations by irradiating the LEU electroplating target in a CIP irradiation position of 36 g causes a reactivity change of 597.724 pcm and a maximum radial power peaking factor of 1.3078. Both of these quantities are within the limits permitted for the safety of the reactor operation.
MANAJEMEN TERAS RSG-GAS BERBAHAN BAKAR SILISIDA 4,5 DAN 4,8 G U/CC Lily Suparlina; Tagor Malem Sembiring
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 4, No 4 (2003): Agustus Edisi Khusus 4 2003
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2003.4.4.1717

Abstract

MANAJEMEN TERAS RSG-GAS BERBAHAN BAKAR SILISIDA 4,5 DAN 4,8 G U/CC. Dengan telah digunakannya bahan bakar silisida 2,96 g/cc di teras RSG-GAS dan telah dilakukannya beberapa penelitian mengenai penggunaan bahan bakar silisida 3,55 g/cc, studi mengenai kemunginan penggunaan bahan bakar silisida dengan densitas yang lebih tinggi perlu dilanjutkan. Densitas uranium maksimum bahan bakar silisida yang telah terkualifikasi adalah sebesar 4,8 g U/cc. Penelitian sebelumnya menyimpulkan bahwa penggunaan bahan bakar silisida dengan densitas 3,55 g U/cc dapat menaikkan panjang siklus sebesar 7 (tujuh) hari daya penuh (210 MWD) dengan tanpa mengubah material dan konfigurasi teras. Namun akan terjadi penurunan margin padam sebesar 50% dibanding dengan desain awal. Dengan demikian penggunaan bahan bakar silisida dengan densitas uranium lebih besar dan 3,55 g U/cc di teras RSG-GAS harus menambahkan batang kendali pengaman (BKP). Penelitian yang dilakukan ialah untuk mendapatkan teras setimbang RSG-GAS silisida berdensitas 4,5 dan 4,8 g U/cc. Perhitungan sel menggunakan paket program WIMS/D4 dan perhitungan teras menggunakan paket perhitungan difusi 2 dimensi BATAN-EQUIL-2D. Perhitungan teras dilakukan untuk kondisi teras setimbang tanpa dan dengan BKP. Hasil perhitungan menunjukkan bahwa teras tanpa BKP tidak dapat dioperasikan, akan tetapi dengan menambahkan BKP, pada posisi B-3 dan G-10, reactor dapat dioperasikan dengan panjang siklus antara 1200-1270 MWD dan 1400MWD masing-masing untuk teras silisida 4,5 dan 4,8 g U/cc.
VALIDASI PAKET PROGRAM NODAL3 UNTUK KASUS STATIS BENCHMARK TERAS REAKTOR PWR Tagor Malem Sembiring; Surian Pinem
GANENDRA Majalah IPTEK Nuklir Volume 15 Nomor 2 Juli 2012
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (623.258 KB) | DOI: 10.17146/gnd.2012.15.2.18

Abstract

VALIDASI PAKET PROGRAM NODAL3 UNTUK KASUS STATIS TERAS BENCHMARK REAKTOR PWR. Persamaan difusi neutron dengan metode nodal telah menjadi metode standar dalam perhitungan parameter neutronik teras reaktor daya air ringan, seperti reaktor air bertekanan (PWR) atau air mendidih (BWR), karena waktu komputasi yang cepat dan hasilnya akurat. Paket program NODAL3 telah dikembangkan untuk menyelesaikan persamaan difusi neutron dengan metode nodal polinom (PNM) dalam geometri 3-dimensi (3-D). Validasi hasil perhitungan NODAL3 untuk kasus statis teras benchmark reaktor PWR (Pressurized Water Reactor), seperti IAEA-2D, BIBLIS, KOEBERG dan IAEA-3D, disajikan dalam penelitian ini. Teras benchmark yang dipilih mewakili kasus 2-D dan 3-D dan mempunyai karaktristik yang berbeda, sehingga dapat menentukan keakuratan NODAL3 dari aspek neutronik yang luas. Parameter neutronik statis yang dihitung adalah faktor perlipatan efektif, keff, faktor puncak daya (FPD) dan profil distribusi FPD ke arah aksial. Dibandingkan dengan acuan, hasil perhitungan NODAL3 menunjukkan bahwa untuk nilai keff terdapat perbedaan maksimum sebesar 0,006% (Δk). Sedangkan untuk FPD radial dan FPD aksial maksimum, selisih maksimum dengan acuan masing-masing sebesar -0,006 dan 0,051. Untuk kasus 3-D, hasil perhitungan NODAL3 konsisten dengan hasil perhitungan paket program nodal tervalidasi PARCS dan NESTLE. Riset ini menunjukkan bahwa akurasi paket program NODAL3 dalam menghitung parameter neutronik teras benchmark reaktor PWR, baik kasus 2-D dan 3-D, menunjukkan hasil yang sangat memuaskan. Oleh karena itu, paket program NODAL3 siap untuk diaplikasikan dalam analisis neutronik reaktor PWR yang riil.Kata kunci : metode nodal, reaktor PWR, teras benchmark, faktor perlipatan efektif, faktor puncak daya
CORE DESIGN OF TRIGA2000 BANDUNG USING U3Si2/Al FUEL ELEMENT MTR TYPE Surian Pinem; Tukiran Surbakti; Tagor Malem Sembiring
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (2018): 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.2018.24.2.4302

Abstract

The TRIGA2000 Bandung reactor currently uses cylinders fuel type, but the fuel production has been discontinued. In order to operate continuously, it is planned that the TRIGA2000 reactor should change the fuel from cylinder type to U3Si2/Al MTR type since Indonesia has been able to produce such fuel element. In this research calculation of TRIGA2000 coreusing U3Si2/Al fuel MTR type of three different fuel densities has been done. This activity begins with performing neutron macroscopic cross section generation for all core materials as a function of temperature, burn up and xenon. The cross-section generation was performed with the WIMSD5 code. The calculation of the core parameters were done with the Batan-FUEL code. Based on the calculation of neutronic parameters, there are three core configurations, i.e.core with 16 fuel elements and 4 control elements (Core 16/4), core with 14 fuel elements and 4 control elements (Core 14/4) and core with 12 fuel elements and 4 control elements (Core 12/4). The three cores meet the safety constraint but only the Core 16/4 that uses U3Si2/Al fuel with a density of 2.96 gU/cm3. The maximum thermal neutron flux in the core center is 5.874×1013 n/cm2s with core cycle length is 245 days at 2 MW. The results show that the TRIGA2000 core can be converted from cylinder type fuel to silicide MTR type.
Co-Authors Iman Kuntoro Iman Kuntoro Lily Suparlina Raden Mohamad Herdian Bhakti Sigit Purwanto Surian Pinem Surian Pinem Tukiran Surbakti Tukiran Tukiran