Preliminary Neutronics Evaluation of 250 MWth MSR with FNaBe Type of Fuel Salt
Cici Wulandari1, Abdul Waris2,*, Sidik Permana2, and Syeilendra Pramuditya2

1Department of Physics, Faculty of Mathematics and Natural Sciences,
Institut Teknologi Bandung, Indonesia
2Nuclear Physics & Biophysics Research Division, Department of Physics and
Department of Nuclear Science & Engineering
Faculty of Mathematics and Natural Sciences,
Institut Teknologi Bandung, Indonesia
Jl. Ganesa 10 Bandung 40132, Indonesia
*E-mail: awaris[at]fi.itb.ac.id

Abstract

FNaBe is one type of molten salts that has been recommended in the Molten Salt Fast Reactor (MSFR). For Molten Salt Thermal Reactor or commonly consider as Molten Salt Reactor (MSR), FLiBe and FLiNaK are considered as a coolant in MSR. Naturally occurring lithium is composed of two stable isotopes, 6Li and 7Li, where the latter being the more abundant (92.5% natural abundance). However, to utilize Li as part of coolant material in MSR, 7Li should be enriched to become 99.995% of abundance in the whole of Li. In this paper, we evaluate the neutronic performance of 250 MWth MSR with FNaBe fuel salt. The Japanese MSR FUJI-U3 has been selected as the basis of the evaluated 250 MWth MSR design with Thorium and Uranium as main fuel nuclides. Several neutronics parameters such as, fuel composition, effective multiplication factor, and conversion ratio will be discussed the full manuscript.

Keywords: FNaBe- MSR- Neutronics- Thorium- Uranium

Topic: Nuclear Science and Engineering