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S. Pinem, S.
Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency, Puspiptek Area, Serpong, Tangerang Selatan 15310, Indonesia
Energy Physics

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Application of Sub-Miniature Fission Chamber Neutron Detector for Neutron Flux Measurement at the RSG-GAS Reactor: Foil Activation Benchmarking Gusman, R.; Agung, A.; Subekti, R. M.; Iswahyudi, F. N.; Susanti, F.; Pinem, S.
Atom Indonesia Article In Press
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1768

Abstract

Accurate neutron flux measurement is essential for reactor characterization and utilization. At the RSG-GAS reactor, previous flux measurements relied on the foil activation method. While this method provides high accuracy, it lacks real-time capability due to its requirement for irradiation, post-irradiation cooling, and subsequent gamma spectroscopy for activity assessment. Direct online measurements of thermal neutron flux in the RSG-GAS reactor irradiation positions were performed using a Sub-Miniature Fission Chamber (SMFC) detector, where the flux was determined from the detector's output current proportional to fission events. This approach offers a viable alternative to the conventional foil activation technique by eliminating its time-consuming process and multiple uncertainty sources. After applying a correction factor obtained from gold foil activation reference measurements and the combined measurement uncertainty was quantified as ± 4.0%, results showed an axial flux distribution peaking at 200 mm height from the bottom of the core with maximum values of 4.997 x 1012 ± 0.199 x 1012 n/cm².s at central iradiation position (CIP E7), 6.212 x 1012 ± 0.248 x 1012 n/cm².s at iradiation position (IP B6), and 2.096 x 1012 ± 0.083x1012 n/cm².s at reflector element with plug (BS+ A2) under 200 kW operation. Radial mapping at 600 mm height from the bottom of the core revealed a maximum flux of 1.230 x 1012 ± 0.049 x 1012 n/cm².s at IP (G7). These results demonstrate that the Sub-Miniature Fission Chamber (SMFC) enables real-time neutron flux monitoring and provides a viable alternative to the conventional foil activation technique.
Development of Burnup Fraction Calibration Curve for the Silicide Fuel Equilibrium Core of the RSG-GAS Reactor Pinem, S.; Sulistyo, F. Y.; Liem, P. H.; Hakim, A. A.; Luthfi, W.
Atom Indonesia Article In Press
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1655

Abstract

The reactivity value of the RSG-GAS research reactor fuel with different burnup levels has been measured. The primary objective of this study is to establish the burnup calibration curve using the equilibrium core reactivity method of the RSG-GAS reactor. The reactivity value of each fuel element was measured at the same position within the reactor core to ensure that the measured burnup corresponds to the experimental core. The reactivity value of each fuel element was then extrapolated with the known burnup of the fuel element. The total control rod worth measurement was compared with Monte Carlo Serpent2 code calculations. The experimental fuel reactivity results were compared with the calculation results, showing a maximum discrepancy of -4.88%. Based on the reactivity measurement and calculation results, a fuel burnup calibration curve was successfully developed, which can be used to determine the burnup fraction of the RSG-GAS reactor.
Co-Authors Agung, A. Gusman, R. Hakim, A. A. Iswahyudi, F. N. Liem, P. H. Luthfi, W. Subekti, R. M. Sulistyo, F. Y. Susanti, F.