Article Per Year (5 Year)
p-Index From 2019 - 2024
0.659
P-Index
This Author published in this journals
All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Spektra: Jurnal Fisika dan Aplikasinya
Surian Pinem
Batan
Aerospace Engineering Electrical & Electronics Engineering Energy Materials Science & Nanotechnology Physics

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

Found 4 Documents
Search

 1 
ANALYSIS OF REACTIVITY INSERTION AS A FUNCTION OF THE RSG-GAS FUEL BURN-UP Tukiran Surbakti; Surian Pinem; Lily Suparlina
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.2021.23.1.6003

Abstract

Analysis of the control rod insertion is important as it is closely related to reactor safety. Previously, the analysis has been carried out in RSG-GAS during static condition, not as a function of the fuel fraction. The RSG-GAS reactor in one cycle is a function of the fuel burn-up. It is necessary to analyze RSG-GAS core reactivity insertion as a function of the fuel burn-up to determine the behavior of the reactor, especially in uncontrolled operations such as continuous pulling of control rods. This analysis is carried out by the computer simulation method using WIMSD-5B and MTR-DYN codes, by observing power behavior as a function of time due to neutron chain reactions in the reactor core. Calculations are performed using point kinetics equation, and the feedback effect will be evaluated using static power coefficient and fuel burn-up function. Analyzes were performed for the core configuration of the core no. 99, by lifting the control rod or inserting positive reactivity to the core. The calculation results show that with the reactivity insertion of 0.5% Δk/k at start-up power of 1 W and 1 MW, safety limit is not exceeded either at the beginning, middle, or end of the cycle. The maximum temperature of the fuel is 135°C while the safety limit is 180°C. The margin from the safety limit is large, and therefore fuel damage is not possible when power excursion were to occur.
NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR Surian Pinem; Tukiran Surbakti; Iman Kuntoro
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 25, No 3 (2019): Oktober, 2019
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (500.016 KB) | DOI: 10.17146/urania.2019.25.3.5576

Abstract

NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR. Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation. During the reactor operation cycle, the position of the control rods will change due to reactivity changes. The purpose of this study is to determine the effect of control rods position on neutronic and thermal-hydraulics parameters in relation to the safety of reactor operation of the TRIGA 2000 reactor using silicide fuel of MTR plate type. Those parameters are power peaking factor, reactivity coefficients, and steady-state thermohydraulic parameters. Neutronic calculations are performed using a combination of WIMSD/5 and Batan-3DIFF codes and for thermal-hydraulics the calculations are done using WIMSD/5 and MTRDYN codes. The calculation results show that the reactivity coefficient values are negative for all control rod positions both at CZP and HFP conditions. The MTC value decreases when the control rod is inserted into the active core while the FTC value increases. The total ppf results and temperature in steady-state rise when the control rods are inserted of into the active core whereby the maximum value occurs at the position of the control rods of 20 cm from the bottom of the active core. The calculation results of ppf, reactivity coefficient, and thermal-hydraulics parameters lay below safety limits, indicating that the TRIGA 2000 reactor can safely use U3Si2-Al silicide fuel as a substitute fuel for cylindrical type fuel.Keywords: neutronic, thermal-hydraulic parameter, control rod effect, TRIGA 2000, silicide fuel.
Core Design TRIGA2000 Bandung Using U3Si2Al Fuel Element MTR Type Surian Pinem; Tukiran Surbakti; Tagor M. Sembiring
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.2018.24.2.4302

Abstract

DESAIN TERAS REAKTOR TRIGA2000 BANDUNG MENGGUNAKAN TIPE ELEMEN BAKAR MTR U3Si2/Al. Reaktor TRIGA2000 Bandung selama ini menggunakan bahan bakar jenis silinder tetapi bahan bakar tersebut tidak diproduksi lagi. Upaya yang dilakukan agar reaktor TRIGA2000 dapat beroperasi secara kontinu maka direncanakan pergantian bahan bakar jenis silinder ke U3Si2/Al jenis MTR karena Indonesia dapat memprodusi bahan bakar tersebut. Dalam penelitian ini telah dilakukan perhitungan desain teras reaktor TRIGA2000  menggunakan bahan bakar MTR jenis U3Si2/Al dengan tiga densitas bahan bakar yang berbeda. Kegiatan ini dimulai dengan melakukan generasi tampang lintang makroskopik neutron untuk semua bahan teras sebagai fungsi temperatur, fraksi bakar dan xenon. Generasi tampang lintang dilakukan dengan program WIMSD5. Perhitungan parameter teras reaktor dilakukan dengan program Batan-FUEL. Berdasarkan hasil perhitungan parameter neutronik ada tiga kemungkinan konfigurasi teras yaitu 16 elemen bakar dan 4 elemen kendali (Core 16/4), teras dengan 14 elemen bahan bakar dan 4 elemen kendali (Core 14/4) dan teras dengan 12 elemen bahan bakar dan 4 elemen kendali (Core 12/4). Ketiga konfigurasi teras ini memenuhi batasan keselamatan operasi tetapi hanya Core 16/4 yang dapat menggunakan bahan bakar U3Si2/Al dengan kepadatan 2,96 g/cm3. Fluks neutron termal maksimum di pusat teras adalah 5,874 × 1013 n/cm2s dan panjang siklus adalah 310 hari pada daya 2 MW. Hasil perhitungan menunjukkan bahwa teras TRIGA2000 dapat dikonversi dari bahan bakar jenis silinder menjadi bahan bakar silisida jenis MTR.Kata kunci: bahan bakar jenis silinder, bahan bakar jenis MTR, Batan-FUEL, fluks neutron termal.
DESIGN OF NEUTRONIC PARAMETERS OF MTR REACTOR USING WIMSD-5B/BATAN-FUEL CODES Tukiran Surbakti; Surian Pinem; Lily Suparlina
Spektra: Jurnal Fisika dan Aplikasinya Vol 5 No 3 (2020): SPEKTRA: Jurnal Fisika dan Aplikasinya, Volume 5 Issue 3, December 2020
Publisher : Program Studi Fisika Universitas Negeri Jakarta

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.21009/SPEKTRA.053.08

Abstract

BATAN has three aging research reactors, so it is necessary to design a new, more modern MTR type reactor using high-density, low enrichment uranium molybdenum fuel. The thermal neutron flux at the irradiation position is an important concern in the design of research reactors. This analysis is performed using standard computer codes WIMSD-5B and Batan-FUEL. The purpose of this study is to analyze the effect of the core configuration with safety control rods and neutronic parameters using the diffusion method calculation. The reactor core consists of 16 fuel elements and four control rods placed in the 5 x 5 position of the grid plate and is loaded the reflector elements outside the core. The cycle length is also a concern, not less than 20 days, and the reactor can be operated safely with a power of 50 MW. The calculation results show that for the highest fuel loading, which is 450 grams of U7Mo/Al fuel with D2O as a reflector, it will provide the lowest thermal neutron flux at the center of the core irradiation position, namely 1.0 x1015 n/cm2s. The core fuel cycle length will be up to 39 days, meeting the expected acceptance and safety criteria.
Co-Authors Iman Kuntoro Lily Suparlina Tagor M. Sembiring Tukiran Surbakti Tukiran Surbakti