Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor

Atom Indonesia

T.M. Sembiring¹  S. Pinem¹  P.H. Liem² 

[1]Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency Puspiptek Area, Serpong, Tangerang Selatan 15310, Indonesia

[2]Nippon Advanced Information Service (NAIS Co. Inc.), 416 Muramatsu, Tokaimura, Ibaraki 319-112, Japan

关键词: ranium foil target;    Coupled neutronic and thermal-hydraulic code;    Safety;    RSG-GAS reactor;    Mo-99;   

DOI  :  dx.doi.org/10.17146/aij.2016.532

来源: DOAJ

【 摘 要 】

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.

【 授权许可】

Unknown