Collection of data on the thermophysical properties of the liquid metal reactor coolant that passes through the reactor core
Year: 2025
Type: report
Abstract: The present study’s objective is the analysis of the conceptual pre-design of a small modular fast neutron nuclear reactor, summarizing the research of recent years in "Sofia University." In establishing the design features, basic principles were used, offering increased safety and also following the perspective of achieving economic justification of the project. The proposed reactor is designed to be simplified as much as possible, freed from moving parts and the corresponding reduction of the possible mechanical damages. To distinguish our proposed design from existing ones, a STAR-PLUS(M) designation has been introduced, derived from the STAR (Secure, Transportable, Autonomous Reactor) concept. The proper fluid flow analysis requires the usage of capable in thermo-hydraulics codes for the investigation of thermal properties of STAR-PLUS(M) core. This report provides a summary and analysis of the important correlations required for thermophysical modeling of the proposed reactor. There are analyzed the thermophysical properties of the following materials: tin (Sn) and lead-tin alloys (Pb40Sn60 and Sn40Pb60). Correlations for the following properties are considered: density, viscosity, thermal conductivity, specific heat capacity, and specific enthalpy, developed/estimated, based on the specificly developed methodology.
Authors: Hammachi, Sonia, Petkov, Plamen
Institutions: Sofia University "St. Kliment Ohridski", Aalto University
Language: English
Subfield: Nuclear Energy and Engineering
Field: Energy
Domain: Physical Sciences
Open Access status: green
Award: G9000363982
OpenAlex ID: W7213633833