A supercritical water cooled reactor (SCWR) is one promising reactor concept selected by the Generation IV International Forum. The design and licensing of such a small-scale fuel assembly with a high pressure coolant loop, involving emergency and auxiliary systems, is the scope of the project SCWR-FQT. In this work, a numerical model of the test facility with all safety-relevant components has been elaborated with the one-dimensional system code APROS.
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