NEUTRONIC ANALYSIS ON IRRADIATION OF THE LEU ELECTROPLATING TARGET IN THE RSG-GAS REACTOR FOR PRODUCTION OF 99MO RADIONUCLIDE

Authors

  • Surian Pinem Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency (BATAN
  • Tagor Malem Sembiring Center for Nuclear Energy System Assessment, National Nuclear Energy Agency (BATAN)
  • Tukiran Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency (BATAN)
  • Iman Kuntoro Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency (BATAN)

DOI:

https://doi.org/10.17146/gnd.2018.21.2.4392

Keywords:

LEU, radioisotope 99Mo, neutronic parameters, RSG-GAS reactor

Abstract

RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research material testing, industry demand, R & D institutions and universities. One of the routine activities performed for RSG-GAS reactor operation is irradiation of LEU targets into the core to produce 99Mo radionuclide. The target insertion in the core will change the neutronic characteristic of the core so it can exceed the safety limits of reactor operation. This paper analyzes the neutronic parameters due to the insertion of the LEU electroplating target into the reactor core irradiation facility. The neutronic parameters for optimizing the LEU electroplating irradiated target are important for the safety of the reactor operation. Neutronic parameter calculations were performed using WIMS/D5 and Batan-3DIFF codes routinely used for RSG-GAS core calculations. Based on calculations by irradiating the LEU electroplating target in a CIP irradiation position of 36 g causes a reactivity change of 597.724 pcm and a maximum radial power peaking factor of 1.3078. Both of these quantities are within the limits permitted for the safety of the reactor operation.

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Published

2026-03-12

How to Cite

Surian Pinem, Tagor Malem Sembiring, Tukiran, & Iman Kuntoro. (2026). NEUTRONIC ANALYSIS ON IRRADIATION OF THE LEU ELECTROPLATING TARGET IN THE RSG-GAS REACTOR FOR PRODUCTION OF 99MO RADIONUCLIDE. Ganendra: Majalah IPTEK Nuklir, 21(2 Juli), 55–61. https://doi.org/10.17146/gnd.2018.21.2.4392

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