Abstract

A simulation suite has been developed to model reactor power distribution and multiphysics feedback effects in Sodium-cooled Fast Reactors (SFRs). This suite is based on the Finite Element Method (FEM) and employs a general, unstructured mesh to solve the Simplified P3 (SP3) neutron transport equations. In the FEM implementation, two-dimensional triangular elements and three-dimensional wedge elements are selected. Wedge elements are selected for their natural description of hexagonal geometry common to fast reactors. Thermal feedback effects within fast reactors are modeled within the simulation suite. A thermal hydraulic model is developed, modeling both axial heat convection and radial heat conduction within fuel assemblies. A thermal expansion model is included and is demonstrated to significantly affect reactivity. This simulation suite has been employed to model the Advanced Burner Reactor (ABR) benchmark, specifically the MET-1000. It has been demonstrated that these models sufficiently describe the multiphysics feedback phenomena and can be used to estimate multiphysics reactivity feedback coefficients.

Highlights

  • Renewed interest in advanced nuclear power reactors, such as the Versatile Test Reactor (VTR) at the Idaho National Laboratory (INL), has encouraged enhanced modeling and simulation of fast nuclear power reactors

  • This is acceptable because the Linear Expansion Factor (LEF) are on the order 10−2 and the reactivity effect of expanding from room-temperature to operating temperatures is more significant than small, local variations in material temperatures

  • The Advanced Burner Reactor (ABR) is a benchmark reactor design proposed by the OECD-NEA [15]

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Summary

INTRODUCTION

Renewed interest in advanced nuclear power reactors, such as the Versatile Test Reactor (VTR) at the Idaho National Laboratory (INL), has encouraged enhanced modeling and simulation of fast nuclear power reactors. In pursuit of this interest, a simulation suite has been developed to simulate fast reactors with an emphasis on Sodium-cooled Fast Reactor (SFR) modeling [1]. Recent additions to this suite include the addition of the Simplified P3 (SP3) equations. All of the multiphysics models are coupled in a power iteration method and use a common geometry mesh

SIMPLIFIED P3 NEUTRON TRANSPORT
THERMAL HYDRAULICS
Axial Convection Model
Radial Conduction Model
Cross Section Treatment
THERMAL EXPANSION
Material Properties
Thermal Expansion Model Details
RESULTS
Advanced Burner Reactor – MET-1000
Reactivity Coefficients
CONCLUSIONS AND FUTURE RESEARCH
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