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Analysis of Neutron Flux Distribution in Rsg-Gas Reactor With U-Mo Fuels

Taswanda, Taryo and T.M., Sembiring (2004) Analysis of Neutron Flux Distribution in Rsg-Gas Reactor With U-Mo Fuels. Atom Indonesia, 30 (1). pp. 21-34. ISSN 0126-1568

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Abstract

The use of U-Mo fuels in research reactors seems to be promising and, recently, world researchers have carried out these such activities actively. The National Nuclear Energy Agency (BATAN) which owns RSG-GAS reactor available in Serpong Research Center for Atomic Energy should anticipate this trend. It is, therefore, this research work on the use of U-Mo fuels in RSG-GAS reactor should be carried out. The work was focused on the analysis of neutron flux distribution in the RSG-GAS reactor using different content of molybdenum in U-Mo fuels. To begin with, RSG-GAS reactor core model was developed and simulated into X, Y and Z dimensions. Cross section of materials based on the developed cells of standard and control fuels was then generated using WIMS-D5-B. The criticality calculations were finally carried out applying BATAN-2DIFF code. The results showed that the neutron flux distribution obtained in U-Mo-fuel-based RSG-GAS core is very similar to those achieved in the 300-gram sillicide-fuel-based RSG-GAS reactor core. Indeed, the utilization of the U-Mo RSG-GAS core can be very similar to that of the high-density sillicide reactor core and even could be better in the future.

Item Type: Article
Subjects: Reaktor Nuklir > Pemanfaatan Reaktor > Teknologi Berkas Neutron
Divisions: Pusat Pendayagunaan Informatika dan Kawasan Strategis Nuklir
Depositing User: USER PPIKSN BATAN
Date Deposited: 23 Dec 2020 15:11
Last Modified: 23 Dec 2020 15:11
URI: http://repo-nkm.batan.go.id/id/eprint/10240

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