PENGARUH DENSITAS URANIUM TERHADAP UMUR BAHAN BAKAR NUKLIR DI DALAM REAKTOR RSG-GAS DITINJAU DARI ASPEK NEUTRONIK

Authors

  • Saga Octadamailah
  • Supardjo

DOI:

https://doi.org/10.17146/urania.2017.23.2.3550

Keywords:

Uranium density, Fuel life, Burn up, Research reactor, Neutronic

Abstract

Material Testing Reactor (MTR) is a research reactor with characteristics: small power, high thermal neutron flux and short life time fuel. Reaktor Serba Guna G.A. Siwabessy (RSG-GAS) located in Serpong is an MTR type reactor initially operated with dispersion fuel of U3O8/Al with uranium enrichment of 19.75 % 235U and uranium density of 2.96 gU/cm3. In an effort to increase the lifetime of nuclear fuel, BATAN has done research on high density uranium fuel starting from U3Si2/Al fule and continued with UMo based fuel in line with investigations performed by worldwide researchers in the field of research reactors. Fuel of U3Si2/Al with a density of 2.96 gU/cm3 has been successfully manufactured and utilized as fuel for RSG-GAS to substitute the U3O8/Al fuel. Post irradiation examination has also been done for U3Si2/Al with a density of 4.8 gU/cm3 up to a burn up of 60 %, while research on UMo with 7 gU/cm3 density has been progressing into mini plate fabrication. Research on high density fuel has been focused on fabrication process, while little has been done on lifetime calculation or utilization period. Therefore, this research has performed a calculation on nuclear fuel lifetime using a paired program of ORIGEN and MCNP. The calculation results show that an increase in uranium density will extend the lifetime of fuel exponentially. The longest lifetime is achieved by UMo type, which extends to 651 days, and this relates to a lifetime extension of 219 days if the RSG-GAS is operated with UMo fuel.

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Published

2024-12-23

How to Cite

Octadamailah, S., & Supardjo. (2024). PENGARUH DENSITAS URANIUM TERHADAP UMUR BAHAN BAKAR NUKLIR DI DALAM REAKTOR RSG-GAS DITINJAU DARI ASPEK NEUTRONIK. Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir, 23(2), 117–126. https://doi.org/10.17146/urania.2017.23.2.3550