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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Ganendra: Majalah IPTEK Nuklir
Surian Pinem
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ANALYSES OF NEUTRON ABSORBER MATERIALS ON THE SAFETY PARAMETERS IN THE RSG-GAS REACTOR Lily Suparlina; Tukiran Surbakti; Surian Pinem; Purwadi Purwadi
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 23, No 2 (2021): June 2021
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2021.23.2.6278

Abstract

Shutdown system in RSG-GAS reactor is using neutron absorber. There are 3 kinds of absorber material in research reactors including Ag-In-Cd alloy, B4C, and Hf. In this works, analyses of different neutron absorbers on the main safety core parameters in the RSG-GAS research reactor are selected for analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, PPF and neutron flux . The RSG-GAS core silicide fuel is selected as the case study to verify calculations. A three-dimensional, four-group diffusion model is selected for core calculations. The well-known WIMSD-5B and Batan-3DIFF reactor codes are used to carry out these calculations. It is found that the largest shutdown margin is gained using the B4C; also the lowest PPF is gained using the Hf material. The maximum point power densities belong to the inside fuel regions surrounding the CIP (centre irradiation position), surrounded by control fuel elements, and the peripheral fuel elements beside the berrylium reflector. The greatest and least fluctuation of the point power densities are gained by using B4C and Ag-In-Cd alloy, respectively.
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.
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
Co-Authors Iman Kuntoro Lily Suparlina purwadi purwadi Raden Mohamad Herdian Bhakti Sigit Purwanto Tagor Malem Sembiring Tukiran Surbakti