Abstract
This paper introduces an extended code package PARCS/RELAP5 to analyze steady state of SCWR US reference design. An 8 × 8 quarter core model in PARCS and a reactor core model in RELAP5 are used to study the core flow distribution under various steady state conditions. The possibility of moderator flow reversal is found in some hot moderator channels. Different moderator flow orifice strategies, both uniform across the core and nonuniform based on the power distribution, are explored with the goal of preventing the reversal.
Highlights
The supercritical water reactor (SCWR) is a generation nuclear reactor concept
Its higher thermal efficiency and considerable plant simplification have distinguished it from the current reactors. Oka and his team presented both a thermal and fast SCWR design [1, 2], and Buongiorno presented a thermal SCWR as the US reference design [3], and Kim et al and Xu et al presented various mixed spectrum SCWR designs [4, 5]
This paper studies flow distributions in steady state using coupled PARCS/RELAP5
Summary
The supercritical water reactor (SCWR) is a generation nuclear reactor concept. Its higher thermal efficiency and considerable plant simplification have distinguished it from the current reactors. Oka and his team presented both a thermal and fast SCWR design [1, 2], and Buongiorno presented a thermal SCWR as the US reference design [3], and Kim et al and Xu et al presented various mixed spectrum (thermal/fast) SCWR designs [4, 5]. This paper uses an extended code package, which couples the core simulator PARCS to the thermal-hydraulics simulator RELAP5, to analyze both steady state and transient of SCWR design. An 8 × 8 quarter core model in PARCS and a reactor core model in RELAP5 [6] are used to study the core flow distribution under various steady state conditions
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