Neutronic Design Of Plutonium Uranium Fuel-Based Gas-Cooled Fast Reactor

Monado, Fiber (2018) Neutronic Design Of Plutonium Uranium Fuel-Based Gas-Cooled Fast Reactor. Jurnal Pendidikan Fisika Indonesia, 14 (2). pp. 92-98. ISSN 1693-1246

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Abstract

This study presents the calculation results of the cell, and core Gas-cooled Fast Reactor (GFR) based fuel UraniumPlutonium Nitride (U, Pu)N. Parameter survey results of calculations of the fuel cell consisting of a kinf, burnup level, and the conversion ratio and for the calculation of the reactor core produce value keff during a refueling cycle. The calculation was performed by using a set of SRAC program by comparing three types of fuel cell designs. Reactor Design A based on natural uranium could not reach criticality because of keff < 1. Design B used the enrichment of uranium-235 by 9.5% to reach a critical condition at keff > 1. The critical state was also achieved by Design C utilizing natural uranium, and plutonium 5.5% result value keff = 1.015 in the first year of burnup and continues to increase 1.083 in the tenth year without refueling. Moreover, plutonium can replace the uranium enrichment process.

Item Type:	Article
Subjects:	Q Science > QC Physics > QC1-999 Physics
Divisions:	08-Faculty of Mathematics and Natural Science > 45102-Physics (S2)
Depositing User:	Dr Fiber Monado
Date Deposited:	19 Jun 2023 23:17
Last Modified:	19 Jun 2023 23:17
URI:	http://repository.unsri.ac.id/id/eprint/111742

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