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All Journal Ganendra: Majalah IPTEK Nuklir Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology)
R. Andika Putra Dwijayanto
Centre for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency
Biochemistry, Genetics & Molecular Biology Computer Science & IT Energy Environmental Science Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology Physics Other

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PRELIMINARY STUDY ON MINOR ACTINIDE INCINERATION IN RSG-GAS WITHOUT ISOTOPE SEPARATION R. Andika Putra Dwijayanto; Muhammad Alfarisie
GANENDRA Majalah IPTEK Nuklir Volume 24 Nomor 2 Juli 2021
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/gnd.2021.24.2.6241

Abstract

Minor actinides (MA) resulted from nuclear power plants is often considered as nuisance in spent fuel management due to its considerably long half-life. One of available strategies to deal with MA is to incinerate it, in order to reduce its radioactivity. This paper presents a study on MA incineration in RSG-GAS research reactor. Unlike previous study, this work did not separate the MA into individual isotopes, but incinerated as a whole. ORIGEN2.1 code is employed to calculate MA incineration within RSG-GAS core. MA composition used in this study consists of Np, Am, and Cm isotopes. The Central Irradiation Position (CIP) of RSG-GAS is loaded by 6 kg of MA and irradiated for two years. The result shows that about 1 kg of MA were incinerated after two years of irradiation, or 18,87% of the initial concentration. However, the increase of Cm-242 isotope, along with newly-formed Pu isotopes, were found to be significantly increasing short-term radioactivity compared to un-irradiated MA. Thus, two years-worth of MA incineration cannot be considered as effective, and other strategies must be pursued.
ASSESSING THE OTTO OPTION: THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL CHARACTERISTICS R. Andika Putra Dwijayanto; Ihda Husnayani; Zuhair Zuhair
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (460.87 KB) | DOI: 10.17146/jstni.2020.21.1.5766

Abstract

Two main refuelling option considered for use in a High Temperature Gas-cooled Reactor (HTGR) are multi-pass and once through-then-out (OTTO) cycle. The former possesses superiority in term of fuel utilisation whilst the latter is considered better in term of system simplicity. HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE) is supposed to adopt multi-pass refuelling scheme. However, OTTO-scheme shall also be considered for the simplicity it offers and thus potentially lower cost. Due to different neutronic and burnup profile between the two, the resulting spent fuel characteristic is also different and possibly requires different handling mechanism. This paper assesses the characteristics of OTTO-scheme RDE spent fuel using thorium fuel cycle. The assessment is performed employing ORIGEN2.1 code. At day 30 of cooling after determined end-of-cycle (EOC), each spent fuel yields 234.9 Curies of radioactivity, emitting 66.26 neutrons/second, 1x1013 photons/second, and releasing 0.7675 watts of decay heat. These numbers must be taken into consideration regarding spent fuel management and spent fuel cask design. Tl-208 isotope characteristics, whose existence is unique to thorium fuel cycle, were also determined. It is found to be yielding 3.42x10-3 Curie of radioactivity and releasing 1.2x108 photons/second at its peak. Understanding its high-energy gamma release, proper radiation protection mechanism must be implemented.
Co-Authors Ihda Husnayani Muhammad Alfarisie Zuhair Zuhair