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

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Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor S. Pinem; T.M. Sembiring; P.H. Liem
Atom Indonesia Vol 42, No 3 (2016): December 2016
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (2548.003 KB) | DOI: 10.17146/aij.2016.532

Abstract

The G. A. Siwabessy Multipurpose Reactor (Reaktor Serba Guna G.A. Siwabessy, RSG-GAS) has an average thermal neutron flux of 2×1014 neutron/(cm2 sec) at the nominal power of 30 MW. With such a high thermal neutron flux, the reactor is suitable for the production of Mo-99 which is widely used as a medical diagnostic radioisotope. This paper describes a safety analysis to determine the optimum LEU foil target by using a coupled neutronic and thermal-hydraulic code, MTR-DYN. The code has been developed based on the three-dimensional multigroup neutron diffusion theory. The best estimated results can be achieved by using a coupled neutronic and thermal-hydraulic code. The calculation results show that the optimum LEU foil target is 54 g corresponding to the reactivity change of less than the limit value of 500 pcm. From the safety analysis for the case when the primary flow rate decreased by 15% from its nominal value, it was found that the peak temperatures of the coolant and cladding are 69.5°C and 127.9°C, respectively. It can be concluded that the optimum LEU foil target can be irradiated safely without exceeding the limit value.Received: 10 December 2015; Revised: 2 August 2016; Accepted: 4 August 2016
Co-Authors P.H. Liem T.M. Sembiring