Open AccessComparatives Studies Of A Safety Analysis For Molten Salt Reactor (MSR)
Author(s) -
Rindi Wulandari,
Sidik Permana
Publication year - 2020
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1493/1/012030
Subject(s) - nuclear engineering , molten salt , coolant , inherent safety , nuclear reactor core , molten salt reactor , heat transfer , nuclear power , transient (computer programming) , engineering , process engineering , environmental science , computer science , mechanical engineering , mechanics , thermodynamics , physics , nuclear physics , operating system
The Generation IV nuclear power system has been developed by the Generation IV Forum (GIF) with its benefits such as highly economical, enhanced safety, low waste production, and proliferation resistant. MSR is one of Generation IV nuclear power system which uses molten salt as a fuel and a coolant, therefore its technology differs from the conventional solid-fuel reactors. In this study, the author focus on the safety characteristic analysis of the MSRs, in which a point kinetic equations and core heat transfer have been modeled by developing a mathematical model for MSRs. The founded model is applied to analyze the safety characteristics of the molten salt actinide recycler and transmuter system (MOSART) by simulating transient basic condition, and that is the unprotected loss of flow (ULOF) and unprotected overcooling accident (UOC). The result of reactor accident simulation is power distribution and temperature in the core reactor toward the time and showing that MOSART conceptual design is a reactor design which is stablee inherently. This reseach purposes to give basic understanding about safety characteristic of the MSR.