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Feasibility study of axial compact neutron generator as SAMOP neutron source

SAMOP is a subcritical assembly for the Mo-99 isotope production. This isotope plays important role as a generator of Tc-99m isotope which is widely used for diagnostic in nuclear medicine. The SAMOP which is developed at PSTA BATAN uses uranyl nitrate solution UO2(NO3)2 as fuel material and also as...

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Main Authors: Pudjorahardjo, Djoko Slamet, Syarip, Wahyono, Puradwi Ismu
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description SAMOP is a subcritical assembly for the Mo-99 isotope production. This isotope plays important role as a generator of Tc-99m isotope which is widely used for diagnostic in nuclear medicine. The SAMOP which is developed at PSTA BATAN uses uranyl nitrate solution UO2(NO3)2 as fuel material and also as target material in the process of Mo-99 production. This process is based on the fission reaction of uranium U-235 contained in the uranyl nitrate solution. The U-235 fission reactions occur as long as there are still neutrons from external neutron source and it will stop whenever the external neutron source is removed. SAMOP needs an external neutron source which can provide neutrons with an average neutron flux of 108 n/cm2s for maintaining the sustainability of U-235 fission reactions. Presently, SAMOP external neutrons need is provided by the neutrons from the radial beam port of the Kartini research reactor. For further development, SAMOP will be equipped with a compact neutron generator as its external neutron source. Compact neutron generator is a kind of neutron generator which has small size compared to conventional neutron generator. Neutron generator produces neutrons by the D-D or D-T fusion reaction. The neutron energy produced by the D-D and D-T fusion reactions are 2.5 MeV and 14.1 MeV respectively. Therefore, the feasibility study of axial compact neutron generator as SAMOP neutron source has been done. Axial compact neutron generator is a kind of compact neutron generator where the position of ion source and target in compact neutron generator is along the axis of the compact neutron generator. The results of the study show that the axial compact neutron generator has a chance to substitute a nuclear reactor as external neutron source of SAMOP. It can produce neutrons which neutron yield is sufficient to meet the neutron need of SAMOP. It depends on the type of the axial compact neutron generator, one of which is the product of The Lawrence Berkeley National Laboratory i.e. the axial compact neutron generator with fully shielded high voltage which can produce neutron yield up to 109 n/s from D-D fusion reaction. The benefit of using axial compact neutron generator as neutron source of SAMOP is that the operational cost will reduce since the neutron production cost using axial compact neutron generator is cheaper than a nuclear reactor. In addition, the operational procedure of axial compact neutron generator is simpler than a nuclear reactor.
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This isotope plays important role as a generator of Tc-99m isotope which is widely used for diagnostic in nuclear medicine. The SAMOP which is developed at PSTA BATAN uses uranyl nitrate solution UO2(NO3)2 as fuel material and also as target material in the process of Mo-99 production. This process is based on the fission reaction of uranium U-235 contained in the uranyl nitrate solution. The U-235 fission reactions occur as long as there are still neutrons from external neutron source and it will stop whenever the external neutron source is removed. SAMOP needs an external neutron source which can provide neutrons with an average neutron flux of 108 n/cm2s for maintaining the sustainability of U-235 fission reactions. Presently, SAMOP external neutrons need is provided by the neutrons from the radial beam port of the Kartini research reactor. For further development, SAMOP will be equipped with a compact neutron generator as its external neutron source. Compact neutron generator is a kind of neutron generator which has small size compared to conventional neutron generator. Neutron generator produces neutrons by the D-D or D-T fusion reaction. The neutron energy produced by the D-D and D-T fusion reactions are 2.5 MeV and 14.1 MeV respectively. Therefore, the feasibility study of axial compact neutron generator as SAMOP neutron source has been done. Axial compact neutron generator is a kind of compact neutron generator where the position of ion source and target in compact neutron generator is along the axis of the compact neutron generator. The results of the study show that the axial compact neutron generator has a chance to substitute a nuclear reactor as external neutron source of SAMOP. It can produce neutrons which neutron yield is sufficient to meet the neutron need of SAMOP. It depends on the type of the axial compact neutron generator, one of which is the product of The Lawrence Berkeley National Laboratory i.e. the axial compact neutron generator with fully shielded high voltage which can produce neutron yield up to 109 n/s from D-D fusion reaction. The benefit of using axial compact neutron generator as neutron source of SAMOP is that the operational cost will reduce since the neutron production cost using axial compact neutron generator is cheaper than a nuclear reactor. 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This isotope plays important role as a generator of Tc-99m isotope which is widely used for diagnostic in nuclear medicine. The SAMOP which is developed at PSTA BATAN uses uranyl nitrate solution UO2(NO3)2 as fuel material and also as target material in the process of Mo-99 production. This process is based on the fission reaction of uranium U-235 contained in the uranyl nitrate solution. The U-235 fission reactions occur as long as there are still neutrons from external neutron source and it will stop whenever the external neutron source is removed. SAMOP needs an external neutron source which can provide neutrons with an average neutron flux of 108 n/cm2s for maintaining the sustainability of U-235 fission reactions. Presently, SAMOP external neutrons need is provided by the neutrons from the radial beam port of the Kartini research reactor. For further development, SAMOP will be equipped with a compact neutron generator as its external neutron source. Compact neutron generator is a kind of neutron generator which has small size compared to conventional neutron generator. Neutron generator produces neutrons by the D-D or D-T fusion reaction. The neutron energy produced by the D-D and D-T fusion reactions are 2.5 MeV and 14.1 MeV respectively. Therefore, the feasibility study of axial compact neutron generator as SAMOP neutron source has been done. Axial compact neutron generator is a kind of compact neutron generator where the position of ion source and target in compact neutron generator is along the axis of the compact neutron generator. The results of the study show that the axial compact neutron generator has a chance to substitute a nuclear reactor as external neutron source of SAMOP. It can produce neutrons which neutron yield is sufficient to meet the neutron need of SAMOP. It depends on the type of the axial compact neutron generator, one of which is the product of The Lawrence Berkeley National Laboratory i.e. the axial compact neutron generator with fully shielded high voltage which can produce neutron yield up to 109 n/s from D-D fusion reaction. The benefit of using axial compact neutron generator as neutron source of SAMOP is that the operational cost will reduce since the neutron production cost using axial compact neutron generator is cheaper than a nuclear reactor. 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This isotope plays important role as a generator of Tc-99m isotope which is widely used for diagnostic in nuclear medicine. The SAMOP which is developed at PSTA BATAN uses uranyl nitrate solution UO2(NO3)2 as fuel material and also as target material in the process of Mo-99 production. This process is based on the fission reaction of uranium U-235 contained in the uranyl nitrate solution. The U-235 fission reactions occur as long as there are still neutrons from external neutron source and it will stop whenever the external neutron source is removed. SAMOP needs an external neutron source which can provide neutrons with an average neutron flux of 108 n/cm2s for maintaining the sustainability of U-235 fission reactions. Presently, SAMOP external neutrons need is provided by the neutrons from the radial beam port of the Kartini research reactor. For further development, SAMOP will be equipped with a compact neutron generator as its external neutron source. Compact neutron generator is a kind of neutron generator which has small size compared to conventional neutron generator. Neutron generator produces neutrons by the D-D or D-T fusion reaction. The neutron energy produced by the D-D and D-T fusion reactions are 2.5 MeV and 14.1 MeV respectively. Therefore, the feasibility study of axial compact neutron generator as SAMOP neutron source has been done. Axial compact neutron generator is a kind of compact neutron generator where the position of ion source and target in compact neutron generator is along the axis of the compact neutron generator. The results of the study show that the axial compact neutron generator has a chance to substitute a nuclear reactor as external neutron source of SAMOP. It can produce neutrons which neutron yield is sufficient to meet the neutron need of SAMOP. It depends on the type of the axial compact neutron generator, one of which is the product of The Lawrence Berkeley National Laboratory i.e. the axial compact neutron generator with fully shielded high voltage which can produce neutron yield up to 109 n/s from D-D fusion reaction. The benefit of using axial compact neutron generator as neutron source of SAMOP is that the operational cost will reduce since the neutron production cost using axial compact neutron generator is cheaper than a nuclear reactor. In addition, the operational procedure of axial compact neutron generator is simpler than a nuclear reactor.</abstract><cop>Melville</cop><pub>American Institute of Physics</pub><doi>10.1063/5.0066258</doi><tpages>7</tpages><oa>free_for_read</oa></addata></record>
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source American Institute of Physics:Jisc Collections:Transitional Journals Agreement 2021-23 (Reading list)
subjects Feasibility studies
Ion sources
Neutron flux
Neutrons
Nuclear fuels
Nuclear medicine
Nuclear reactors
Operating costs
Production costs
Uranium
Uranium dioxide
title Feasibility study of axial compact neutron generator as SAMOP neutron source
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