Optimization study and neutronic design calculations of LEU fuelled homogeneous aqueous solution nuclear reactors for the production of short lived fission product isotopes

Mahmood, Tayyab; Iqbal, Masood

doi:10.1016/j.anucene.2011.10.014

Cited by 6 publications

(2 citation statements)

References 6 publications

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“…Studies in optimizing the irradiation target in the research reactor have been carried out, so the reactor operation to be more economic [2][3][4]. For RSG-GAS reactor, the similar studies have been carried out, further, specifically to the single or multi targets [5,6].…”

Section: Sg-gas (Reaktor Serba Guna-ga Siwabessy) Is a Multi-purpose Reactor Based On The Open Pool Mtr (Materials Testingmentioning

confidence: 99%

Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Pinem

Sembiring²,

Tukiran³

et al. 2018

gnd

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Neutronic analysis on irradiation of the LEU electroplating target in the RSG-GAS reactor for production of 99 Mo radionuclide. RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research material testing, industry demand, R & D institutions and universities. The irradiation of the LEU target on the reactor core to produce 99 Mo radioisotope is one of the routine activities of RSG-GAS reactor operation. The target insertion in the core will change the neutronic characteristic of the core so it can exceed the safety limits of reactor operation. The neutronic parameters due to the insertion of the LEU electroplating target into the reactor core irradiation facility is analyzed in this paper. 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 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. The values are within the limits permitted for the safety of the reactor operation i.e. the maximum reactivity change and radial power peaking factor of 2000 pcm and 1.4, respectively.

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Section: Sg-gas (Reaktor Serba Guna-ga Siwabessy) Is a Multi-purpose Reactor Based On The Open Pool Mtr (Materials Testingmentioning

confidence: 99%

Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Pinem

Sembiring²,

Tukiran³

et al. 2018

gnd

View full text Add to dashboard Cite

show abstract

“…Currently most of 99 Mo is being produced in research and test reactors by the irradiation of targets containing enriched fissile material 235 U [5]. 99 Mo is extracted using an acidic process [6].…”

mentioning

confidence: 99%

Analysis of <sup>99</sup>Mo Production Capacity in Uranyl Nitrate Aqueous Homogeneous Reactor using ORIGEN and MCNP

et al. 2014

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Characterization of neutronic parameters and radiation shielding design for an aqueous homogeneous reactor

Jandaghian,

Choopan Dastjerdi,

Mokhtari

2024

Nuclear Engineering and Design

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Optimization study and neutronic design calculations of LEU fuelled homogeneous aqueous solution nuclear reactors for the production of short lived fission product isotopes

Cited by 6 publications

References 6 publications

Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Analysis of <sup>99</sup>Mo Production Capacity in Uranyl Nitrate Aqueous Homogeneous Reactor using ORIGEN and MCNP

Characterization of neutronic parameters and radiation shielding design for an aqueous homogeneous reactor

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